ML19253A250
| ML19253A250 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/14/1979 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| GD-79-2050, NUDOCS 7908200383 | |
| Download: ML19253A250 (29) | |
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Carolina Power & Light Company August 14, 1979 FILE:
NG-3514(B)
SERIAL: GD-79-2050 Office of Nuclear Reactor Regulation ATTENTION:
Mr. T. A.
Ippolito, Chief Operating Reactors Branch No. 3 United States Nuclear Regulatory Commission Washington, D. C.
20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT - CORPORATE ORGANIZATIONAL CHANGES,
Dear Mr. Ippolito:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90 and Part 2.101, Carolina Power & Light Company (CP&L) 'aereby requests revisions to the Technical Specifications for its Brunswick Steam Electric Plant (BSEP) Unit Nos. I and 2.
These revisions reflect corporate organizational changes all of which are administrative in nature; some of the changes were effective on June 1, 1979, and others will become effective on September 1, 1979.
These most recent changes have superseded our August 14, 1978 corporate reorganization submittal.
Therefore, we have prepared the attached package to include all applicable changes.
Please review the attached revised package in lieu of our August 14, 1978 submittal.
No additional fee should be required since this submittal supersedes the August 14, 1978 submittal which has not yet been acted on by the Staff.
Enclosed are the revised pages for the Brunswick Units 1 and 2 technical specifications which reflect these revisions.
Changes are indicated by vertical lines in the right-hand margins of the affected pages.
Some pages will only be effective through August 31, 1979 and are denoted by (Prime) printed after the page number.
Some pages are not to become effective until September 1, 1979 and are so noted.
The remaining pages show neither of these notations and should become effective as soon as possible.
As before, Mr. J. A. Jones remains as the Chief Operatind Officer for CP&L and is the addressee for of ficial correspondence from the NRC.
His title, however, is now Senior Executive Vice President.
I am now Executive Vice President - Power Supply & Customer Services.
My former position, Senior Vice President - Power Supply, is now held by Mr.
D. V. Menscer.
804 043 u.
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_ ~ ~ ' 7908200 Effective September 1, 1979, there will be a new Department of Nuclear Safety and Research, headed by Dr. T. S. Elleman.
This new department will include the functions of Research, Health Physics, and Corporate Nuclear Safety and Quality Assurance Audit.
If you have any questions on these matters, please contact our staff.
Yours very truly,
- 1 f}
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- 1 E. E. Utley Executive Vice President Power Supp.y & Customer Services D\\?i: p f b Attachments Swcrn to and subscribed before me this 14th day of August, 1979.
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant fianager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsi-bility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.l-l(Prime).
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FACILITY STAFF C.2.2 The Facility organization shall be as shown on Figures G.2.2-1 and 6.2.2-? and:
Each on duty shift shall be composed of at least the minimum a.
shif t crew composition shown in Table 6.2.2-1.
b.
At least one licensed Operator shall be in the control room for each reactor containing fuel, At least two licensed Operators shall be present in the c.
control room for each reactor in the process of start-uo, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified to implement radiation pr.otection procedures shall be on site when fuel is in either reactor.
All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation.
f.
A Fire Brigade of at least five members shall be maintained onsite at all times.
The Fire Brigade shall not include the minimum shift crew shown in Table 6.2.2-1 or any personnel required for other essential functions during a fire emergency.
804 045 BRUNSWICK - UNIT 2 6-1 (Prime)
Effective date,:6/1/79-8/31/79
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shail delegate in writing the succession to this responsi-bility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as showl on Figure 6.2.1-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2.2-1 and 6.2.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1.
b.
At least one licensed Operator shall be in the control room for each reactor containing fuel.
At least two licensed Operators shall be present in the c.
control room for each reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor.
All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation.
f.
A Fire Brigade of at least five members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew shown in Table 6.2.2-1 or any personnel required for other essential functions during a fire emergency.
804 0416 BRUNSWICK - UNIT 2 6-1 Effective date: 9/1/79
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Senior Executive Vice President President and and Chief Operating Officer Chief Administrative Officer
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"ANAGEMENT ORGA'!IZATION CHART 4[
FIGURE 6.2.1-1(Prime)
Effective dates:
BRlR?SWICK - IINIT 2 June 1, 1979 - Au ust 31,1979 6-2(P & e)
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MANAGEMENT ORGA'iIZATION CllART FIGl'RE 6. 2.1-1 BRUSSWICR - UNIT 2 69~
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c Figure 6.2.2-1
ADMIfilSTRATIVE C0:lTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the mini-mli fications of AtiSI til8.1-1971 for comparable position, except nu for the Radiation Protection Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAlt1It!G 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator and shall meet or exceed the requirements and recommendations of Section 5.5 of At4SI ill8.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Fire Chief and shall meet or exceed the require-ments of Section 27 of the T1FPA Code-1975.
6.5 REVIEW Atl0 AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)
FUNCTION 6.5.1.1 The PNSC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Pt4SC shall be composed of the:
Chairman:
Plant fianager Vice Chairman:
Operations-Maintenance or Technical-Administrative Superintendent Secretary:
Administrative Supervisor Member:
Maintenance Supervisor (I&C) l Member:
Engineering Supervisor Member:
Environmer.tal and Radiation Control Supervisor Member:
Quality Assurance Supervisor Member:
Operating Supervisor Member:
Maintenance Supervisor (Mechanical)
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PNSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PilSC activities at any one time.
BRUNSWICK - UNIT 2 6-6 804 050
ADMINISTRATIVE CONTROLS MEETING FREQUEf1CY 6.5.1.4 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairtaan or his designated alternate.
QUORUM 6.5.1.5 A quorum of the Pf1SC shall co Chairman and three members including a,nsist of the Chairman or Vice lternates.
RESPONSIBILITIES 6.5.1.6 The PNSC shall be responsible for:
Review of 1) all procedures required by Specification 6.8 and a.
changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant 11anager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety, Review of all proposed changes to Technical Specifications.
c.
d.
Review of all proposed changes or nodifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Nuclear Generation and to the Manager - Corporate Nuclear Safety and Quality Assurance Audit.
f.
Review of all events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notificath to the Comni s sion.
9 Review of facility operations to' detect potential safety hazards.
h.
Perfomance of special reviews, investigations and reports thereon as requested by the Manager - Corporate fluclear Safety and Quality Assurance Audit.
BRUNSWICK - UtilT 2 6-7 804 051
.c ADMI!ilSTRATIVE C0iiTROLS RESPONSIBILITES (Continued) i.
Review of the Plant Security Plan and implementing procedures.
j.
Review of the Emergency Plan and implementing procedures.
AUTHORITY 6.5.1.7 The PMSC shall'.
Recommend to the Plant Manager written approval or disapproval a.
of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the fianager of c.
Nuclear Generation and the fianager - Corporate fluclear Sa fety and Quality Assurance Audit of disagreement between the PfiSC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreemenr.s pursuant to 6.1.1 above, RECORDS 6.5.1.8 The PNSC shall r?aintain wri ten minutes of each meeting and copies shall be provided to the Manager of fluclear Generation and to the Manager - Corporate f;uclear Safety and Quality Assurance Audit.
BRUNSWICK - UtlIT 2 6-8 804 052
AD:11N1STRATIVE CONTROLS 6.5.2 Corporate Nuclear Safety 6 Ouality Assurance Audit Section (CMS & OAAS)
Responsibility 6.5.2.1 The Manager - Corporate Nuc1 car Safety 6 Quality Assurance Audit under tie Vice President-System Planning & Coordination is charged with the overall responsibility for administering the indepe. dent off-site review and quality assurance audit programs as follows:
Approves selection of the individual (s) to conduct off-a.
site safety reviews and quality assurance audits.
b.
Has access to the plant operating records and operating personnel in performing the independent reviews and quality assurance audits.
Prepares and retains written records of revicus and c.
audits.
d.
Assures independent safety reviews are conducted on all items required by Section 6.5.3.3 and quality assurance audits cover all the items included in Section 6.5.4.1.
Distr.butes reports and other records to appropriate e.
managers.
6.5.3
_ Corporate Nuclear Safety Unit Function BRUNSWICK-UNIT 2 6-9 (Prime)
Effective dates:6/1/79-8/31/79
ADMINISTPaTIVE CONTRO:,S 6.5.2 Corporate t;uclear Saf ety & Quality Assurance Audit Section (CNS & OAAS)
Fesponsibility 6.5.2.1 The Manager - Corporate Nuclear Safety & Quality Assurance Audit under the Vice " resident-Nuclear Safety and Research is charged with the overall responsibility for administering the independent off-site review and quality assurance audit programs as follows:
Approves selection of the individual (s) to conduct off-a.
site safety reviews and quality assurance audits.
b.
Has access to one plant operating records and operatin; personnel in performing the independent reviews and quality assurance audit,.
Prepares and retains written records of reviews and c.
audits.
d.
Assures independent safety reviews are conducted on all items required by Section 6.5.3.3 and quality assurance audits cover all the items included in Section 6.5.4.1.
Distributes reports and other records to appropriate e.
managers.
6.5.3 Corpora te t;ucicar Saf ety Unit Function 804 054 BRL'NSWICK-UNIT 2 6-9 Effective date: 9/1/79 l
ADMINISTRATIVE CONTROLS 6.5.3.1 The Corporate Nuclear Safety Unit of the Corporate Nuclear
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Safety & Quality Assurance Audit Section shall provide independent off-site review of significant plant changes, tests, and procedures; verify that reportable occurrences are promptly investigated and corrected in a manner which reduces the probability of recurrence of such events; and detect trends which may not be apparent to a day-to-day obserser.
Personnel 6.5.3.2 a.
Personnel assigned responsibility for independent reviews shall be specified in technical disciplines, and shall collec-tively have the experience and competence required to review problems in the following areas:
1.
Nuclear power plant operations 2.
Nuclear engineering 3.
Chemistry and radiochemistry 4.
Metallurgy 5.
Instrumentation and control 6.
Radiological safety 7.
Mechanical and electrical engineering 8.
Administrative controls 9.
Seismic and environmental 10.
Quality assurance pr etices b.
The following minimum experience requirements shall be es-stablished for those persons involved in the independent off-site safety rr. view program:
BRD;SWICK-UNIT 2 804 055 6-10
A F INISTRATTVF C0hTROLS 1.
Manager of CNS & QAAS - Bachelor of Scienct
..igineering or related field and ten (10) years relat.u experience including five (5) oar, involvement with operation and/or design of nuclear power plants.
2.
Reviewers - Bachelor of Science in engineering or related field or equivalent and five (5)' years related experience including three (3) years involvement with operation and/or design of nuclear power plants, c.
An individual may possess competence in more than one specialty area.
If officient expertise is not available within the Corporate Nuclear Safety Unit, competent individuals from other CP&L organizations or outside consultants shall be utilizsc in performing independent off-site reviews and investigations.
d.
At least three persons, qualified as discussed in Specifica-tion 6.5.3.2.b, will review each item submitted und the
. requirements of 6.5.3.3.
c.
Independent safety reviews shall be perfor-.d by personnel not directly involved with the activity or responsible f or the activity.
S_uy ects Requiring Independent Review 6.5.3.3 The f ollowing subj ects shall be reviewed by the Corporate Nuclear Safety Unit:
BRUNSWICK-UNIT 2 6-11 834 056
A n'fiNI STiWt i \\'r CONT 901 %
Written safety evaluatio 3 of changes in the facility as a.
described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report and tests or experi-ments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1).
This review is to verify that such changes, tests, or experiments did not involve a change in the technical specifications or an unreviewed safety quest on as defined in 10 CFR 50.59(a)(2),
b.
Proposed changes in procedures, proposed changes in the facility, or proposed tests or experiments, any of which involves a change in the technical specifications or an unreviewed safety ques-tion pursuant to 10 CFR 50.59(c). Matters of this kind shall be referred te th: Corporate Nuclear Safety Unit by the Plant Nuclear Saf2ty Committee following its review, or by other functional crganizational units within Carolina Power & Light Company (CP&L) prior to implementation.
Changes in the technical specifications or license amendments c.
relating to nuclear safety prior to implementation, except in those cases where the change is identical to a previously reviewed propesed change.
d.
Violations, deviations and reportable events, which require reporting to the NRC within 24 1.
and as defined in the plant technical specifications such as:
1.
Violations of applicable codes, regulations, orders, technical specifications, license requirements or internal procedures or instructions havi.g safety significance; 804. W and BRUNSWICK-USIT 2 6-12
ADMINISTRATIVE CONIROLS 2.
Significant oper.' ting abnormalities or deviations from normal or expected performance of plant safety-related structures, systems, or components.
Review of events covered under this paragraph shall include the results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the pcobability of recurrence of the event.
Any other matter involving safe operation of the nuclear e.
power plant which the Manager - Corporate t;uclear Safety
& Quality Assurance Audit Section deems appropriate for consideration, or which is referred to the Manager -
Corporate Nuclear Safety 6 Quality Assurance Audit Section by the onsite operating organization or by other functional organizational units within Carolina Power & Light Company.
Follow-up Action 6.5.3.4 Results of Corporate Nuclear Safety (CNS) reviews, including recommendations and concerns will be documented, Copies of the documented review will be retained in the n.
Corporate Nuclear Safety & Quality Assurance Audit Section files.
b.
Recom.nendations and concerns will be submitted to the Manager-Nuclear Generation within 14 days of determination.
A summation of Corporate Nuclear Safety recommendations c.
and concerns will be submitted to the Chairman / Chief Executive BRUNSWICK-UNIT 2 6-12a 804 058
[ AD:!INISTRATIVE CONTROLS -
t Officer; Chief Operating Officer; Executive Vice President-Power Supply and Customer Services; Senior Vice President-Power Supply; Vice President-System Planning & Coordination; Plant Manager; and others, as appropriate on at least a bi-monthly frequency.
6.5.3.5 The Corporate Nuclear Safety Unit review program shall be conducted in accordance with written, approved procedures.
6.5.4 operation & Maintenance Unit Function 6.5.4.1 The Operation & Maintenance Unit of the Corporate Nuclear Safety 6 Quality Assurance Audit Section chall perform audits of plant activities.
These audits shall encompass:
The conformance of facility operation to all provisions a.
, contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The training and qualifications of the entire facility staff at least once per year.
The results of actions taken to correct deficiencies c.
occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months, d.
The verification of compliance and implementa tion of the requirements of the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per two years.
BRUNSWICK-UNIT 2 6-12b (psg Effective dates:6/1/79-8/31/79
[_AD'1TNISTRATIVE CONTROLS Officer; Chief Operating Officer; Executive Vice President-Power Supply and Customer Services; Senior Vice President-Power Supply; Vice President-Nuclear Safety and Research;
~
Plant Manager; and others, as appropriate on at least a bi-monthly frequency.
6.5.3.5 The Corporate Nuclear Safety Unit review program shall be conducted in accordance with written, approved procedures.
6.5.4 Operation 6 Maintenance Unit Function 6.5.4.1 The Operation 6 Maintenance Unit of the Corporate Nuclear Safety 6 Quality Assurance Audit Section shall perform audits of plant activities.
These audits shall encompass:
The conformance of facility operation to all provisions a.
contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The training and qualifications of the entire facility staff at least once per year.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months, d.
The verification of compliance and implemen ta tion of the requirements of the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per two years.
804 060 BRUI:SWICK-UNIT 2 6-12b Effective date: 9/1/79
AUMINISTRAT1VL CONFROLS e.
The Emergency Pian and implementing procedures at least once per two years.
f.
Tne Security Plan and implementing procedures at least once per two years.
g.
The Facility Fire Protection Program and implementing procedures at least once per two years.
h.
Any other area of facility operation considered appropriate by the Corporate Quality Assurance Audit Operation 6 Main-tenarce Unit, the Executive Vice President-Power Supply and Customer Services, or the Senior Vice President-Power Supply.
Personnel 6.5.4.2 a.
Audit personnel will be independent of the area audited.
Selection for auditing assignments is based on experience or training which establishes that their qualifications are commensurate with the complexity or special nature of the ac-tivities to be audited.
In selecting auditing personnel, consideration will be given to special abilities, specialized technical training, prior pertinent experience, personal characteristics, and education.
b.
Qualified outside consultants or other individuals independent from thote personnel directly involved in plant operation, but within the Operations Groups will be used to augment the audit teams when necessary.
BRE?SiICK-UNIT 2 B04. 061
ADMINISTRATIVE CONTROLS Reports 6.5.4.3 Results of audit are approved by the Manager - Corporate Nuclear Safety 6 Quality Assurance Audit Section and transmitted directly to the Company Chairman / Chief Executive Officer, the Chief Operating Officer, the Executive Vice President-Power Supply and Customer Services, the Senior Vice President-Power Supply, and the Vice President-System Planning & Coordination, and others as appropriate, within 30 days after the completion of the audit.
6.5.4.4 The corporate quality assurance audit program shall be conducted in accordance with written, approved procedures.
6.5.5 0UTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months Jtilizing an outside fire protection firm.
6.5.5.2 An inspection and audit of the fire protection and loss prevention l
program shall be performed by a qualified outside fire consultant at least once per 36 months.
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BRUNSWICK-UNIT 2 6-13 (Prime)
Effective dates:6/1/79-8/31/79
ADMINISTRATIVE CONTROLS peports 6.5.4.3 Results of audit are approved by the Manager - Corporate Nuclear Safety & Quality Assurance Audit Section and transmitted directly to the Company Chairman / Chief Executive Officer, the Chief Operating Officer, the Executive Vice President-Power Supply and Customer Services, the Senior Vice President-Power Supply, and the Vice President-Nuclear Safety and Research, and others as appropriate, within 30 days after the completion of the audit.
6.5.4.4 ihe corporate quality assurance audit program shall be conducted in accordance with written, approved procedures.
6.5.5 0UTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention progran inspection and audit shall be performed at least once per 12 months utilizing an outside fire protection firm.
An inspection and audit of the fire protection and loss prevention l
6.5.5.2 program shall be performed by a qualified vatside fire consultant at least once per 36 months.
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BRUNSWICK-UNIT 2 6-13 Effective date: 9/1/79
ADMIN 5TRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTACLE OCCURRENCES:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to t he Commission shall be reviewed by the PNSC and submitted to Manager - Corporate Nuclear Safety and Quality Assurance Audit and the Manager of Nuclear Generation.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT SHUTDOWN within two hours, b.
The Safety Limit violation shall be reported to the Commission, the Manager Nuclear Generation and to the Manager - Corporate Nuclear Safety and Quality Assurance Audit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Sa fety Limit Violation Report shall be prepared.
The report shall be reviewed by the PNSC.
This report shall describe (1) applicable circumstances preceding the violation, (2) ef fects of the violaticn upon facility components, sys tems or struc-tures, and (3) corrective action taken to prevent recurrence.
d.
The Sa fety Limit Violation Report shall be submitted to the Connission, the Manager - Corporate Nuclear Sa fety and Quality Assurance Audit and the Manager of Nuclear Generation within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.
b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protectio 1 Program impl ementa tion.
BRUNSWICK - UNIT 2 6-14 g4
ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
Records and drawing changes reflecting facility design modifi-a.
cations made to systems and equipment described in the Final Sa fety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, Records of facility radiation and contamination surveys.
c.
Records or radiation exposure for all individuals entering radiation control areas.
Records of gaseous and liquid radioactive material released to e.
the environs.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7.1-1.
g.
Records of reactor tests and experiments.
h.
Records of training and qualification for current members of the plant staff.
i.
Records of in-service inspections performed pursuant to these Technical Specifications.
j.
Records of Quality Assurance activities required by the QA Manual.
k.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
Records of meetings of the PNSC and of the previous off-site I*
review organization, Company Nuclear Safety Committee (CNSC).
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
BRUNSWICK - UNIT 2 6-20 804 065
Obiective This section describes the administrative controls and procedures necess.ary to implement the Environmental Technical Specifications.
5.1 ORGANIZATION ANJ REVIEW The Plant Manager is directly responsible for the safe operation of the facility as shown in Figure 5.1-1(Prime). In all matters pertaining to the l
operation of the plant and to the Environmental Technical Specifications, the Plant Manager is directly responsible to the Manager of Nuclear Generation.
The Environmental and Radiation Control Supervisor is directly responsible to the Plant Manager for all Environmental Technical Specifications applicable to the plant, radiological and otherwise.
In the Generation Department, the Manager - Generation Services, Harris Energy & Environmental Center Section, and his staff function in a staf f capacity to assist in the proper implementation of the Environmental Technical Specifications.
neview of plant operations and the technical specifications shall be accomplished by the Plant Nuclear Safety Committee -(PNSC) and the Corporate Nuclear Safety (CN8) Unit as organizationally described in Appendix A to the facility operating license.
Independent off-site QA audits of plant operations shall be performed by the Operation &
Maintenance (0&M) Unit as cescribed in Appendix A to the facility operacing license.
Review and audit functions are defined as follows:
Review by PNSC and CNS of proposed changes to the Environmental a.
Technical Specifications and the evaluated impact of the change.
804 066 5-1 (Prime)
APPENDIX B Amendment No. 28 BSEP 2 Effective dates:6/1/79-8/31/79 l
Obiective This section describes the administrative controls and procedures necessary to implement the Environmental Technical Specifications.
5.1 ORGANIZATIO" AND REVIEW The Plant Manager is directly responsible for the safe operation of the facility as shown in Figure 5.1-1.
In all matters pertaining to the operation of the plant and to the Environmental Technical Specifications, the Plant Manager is directly responsible to the Manager of Nuclear Generation.
The Environmental and Radiation Control Supervisor is directly responsible to the Plant Manager for all Environmental Technical Sorcifications applicable to the plant, radiological and otherwise.
In the Generation Department, the Manager - Generation Services, Harris Energy & Environmental Center Section, and his staff function in a staff capacity to assist in the proper implementation of the Environnental Technical Specifications.
Review of plant operations and the technical specifications chall be accomplished by the Plant Nuclear Safety Committee (PNSC) and the Corporate Nuclear Safety (C"S) Unit as organizatienally described in Appendix A to the facility operating license.
Independent off-site qA audits of plant operations shall be performed by the Operation &
Maintenance (0&M) Unit as described in Appendix A to the facility operating license.
Review and audit functions are defined as follows:
Review by PNSC and CF.S of proposed changes to the Environmental a.
Technical Specificaticns and the evaluated impact of the chanse.
804 067 5-1 APPENDIX B Amendment No. 28 BSEP 2 Effective date: 9/1/79
CIIAIR'IAN/CilIEF EXECUTIVE OFFICER OPERATIO'!S ADMINISTRATION Senior Pxecutive Vice President President and and Chief Operating Officer Chief Administrative Officer
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!!ANAr;EMENT OP/;Ali1ZATION CllART Figure 5.1-] (Prime)
Erfeetivo dates:
BRUT!SWICK - IR;IT 2 b ne 1, 1970 - August 31,1079
CllAIPJLC/CllIEF EXECUTIVE OFFICER OPERATIONS Senior Executive Vice Preside;<
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b.
Review by ?NSC and CNS of ch4nges or =odifications to plant syste=s or equipmen: which are de:er=ined by the Plant Manager to have a sigrifican: adverse effect on the environ =ent and the evaluated i= pact of the change.
Review by ?NSC and CNS of wri::en procedures and changes c.
thereto as described in See: ion 5.3.2 which are dete: ined by the Plan: Manager to detri=en: ally affect the. plant's enviren= ental i= pact.
d.
Investiga:1cn by the ?NSC of reported instances where an environ = ental protection 11=1: is e=ceeded or the occur-rence of an unusual enviren= ental event associa:ed with operation of the plan: which involves a significan:
enviren= ental i= pact.
The report and rec _ endations :ha:
result fren the PNSC investiga:1cn will be reviewed by the CNS.
Corporate quality assurance audi: of plant operations and wri::en e.
procedures for i ple=en:ation of these Technical Specifica:icns by O&M.
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- 5. 1.1 An environ = ental even shall be reported prc=ctly :
the Manager of Nuclear Ganeration and reviewed by the Plan Suclear Safety Cc d::ee.
- 'he Plan:
Manager shall take action :o aba:e any i= pact, i==ediately following his deter =ina:ic of appropria:e ac:1cn per=1::ed by :he technical specifica:icus.
5.2.2 As specified in Section 5.4.2, a report of each environ = ental even: shall be reviewed by the Plan:
Nuclear Safety Co d::ee.
'~his report shall include an evaluation of the cause of the event, a record of the corrective action taken, and the reco==endations for appropriate action to prevent or reduce :he probability of a reenrrence.
804
- 070, Amendment 29 BSEP 2 Appendix B
5.2.3 Copies of all such repcrts shall be aub=1tted to the Manager of Nuclear Generation and the Manager of Corporate Nuclear Safety and Quality Assurance Audit Section for review.
5.2.4 The circu= stances of any environmental event shall be reported to the NRC as specified in Section 5.4.2.
5.3 0?EFJCING ?ROCCURES 5.3.1 Wri::en procedures shall be prepared and approved as specified in See:1on 5.3.2 for operation to ensure co=pliance with the environmental protection conditions and associated surveillance require =en:s of Sections 2 and 3.
Procedures will include sa=pling, analysis, and actions to be taken when environ =en:al protec: ion conditions are e=ceeded.
Quali:7 assurance procedhres will be developed for =enitoring, sa=ple collection, and sa=ple analysis.
Testing frequency of any alar =s will also be included.
5.3.2 Procedures described in See: ion 5.3.1 abcve, and changes thereto, deter =ined by the Plant Manager to detri=entally affect the plant's environ = ental i= pact, shall be reviewed as specified in See:1on 3.1 and approved by the Plan: Manager prior to i=ple=entation.
Te=porary changes to procedures which do not change the intent of the original procedure =ay be =ade, provided such changes are approved by rvo =e=bers of
- he plant nanage=ent staff.
Such changes shall be docu-nented, and subsequently reviewed by the Plan Nuclear Safety Co==1::ee and approved by the Plant Manager prior :o i=cle-
=entation as per=anent procedure changes.
5.3.3 Procedures described in Section 5.3.1 above, and changes thereto, which are deter =ined by the Plant Manager to not detri-
=entally affect the plant's environ = ental i= pact shall be reviewed and approved by the Plan: Manager or other member of the plant
=anage=ent staff designated by :he Plan Manager prior to t=ple-nentation.
5.3.4 Written procedures shall be prepared and approved 804 07i BSEP 2 Appendix B 5-3 Amendment 29
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation arJ shall delegate in writing the succession to this responsi-bility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.i-l(Prime).
l FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2.2-1 and 6.2.2-2 and:
Each on duty shift shall be composed of at least the minimum a.
shi f t crew composition shown in Table 6.2.2-1.
b.
At least one licensed Operator shall be in the control room for each reactor containing fuel <
At.least two licensed Operators shall be present in the c.
control roor.: for each reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities durir:q this operation.
f.
A Fire Brigade of at least five members shall be maintained onsite at all times.
The Fire Brigade shall not include the minimum shift crew shown in Table 6.2.2-1 or any personnel required for other essential functions durin a fire emergency, 804 072 BRUNSWICK-UNIT 1 6-1(Prime)
Effective dates:6/1/79-8/31/79
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsi-bility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.1-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2.2-1 and 6.2.2-2 and:
Each on duty shift shall be composed of at least the minimum a.
shift crew composition shown in Table 6.2.2-1.
b.
At least one licensed Operator shall be in the control room for each reactor containing fuel.
At least two licensed Operators shall be present in the c.
control room for each reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor.
All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation.
f.
A Fire Brigade of at least five members shall be maintained onsite at all times.
The Fire Brigade shall not include the minimum shift crew shown in Table 6.2.2-1 or any personnel required for other essential functions during a fire emergency.
804 073 BRUNSWICK-UNIT 1 6-1 Effective date: 9/1/79
C11 AIR'1AN/ CHIEF EXECUTIVE OFFTCER OPERAT T O';S ADt11NISTRATION Senior Executive Vice President President and ind Chief Operating Of ficer Chief Adminis.:rative Of ficer
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J4 MANAGEMENT OP.GA'i1Z ATI0ti CllART FIGURE 6.2.1-1(Prime)
Effective datos:
BRU';SWICK - UNIT 1 J une 1, 1979 - August 31,1079 p
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804 075 MANAGEMENT ORGANIZATIO" CllART FIGURE 6.2.1-1 Effective date Sept. 1, 1979 j
BRUNSWICK - UNIT 1 6-2
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICAT10t15 6.3.1 Each member of the facility staff sbS11 meet or exceed the mini-mum qualifications of AtiSI N18.1-1971 for comparable position, except for the Radiation Protection Supervisor who shall meet or exceeu the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINI!4G 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator and shall meet or exceed the requirements and recommendations of Section
- 5. 5 o f ANSI l118.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Fire Chief and shall meet or exceed the require-ments of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)
FUNCTION 6.5.1.1 The P!1SC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PNSC shall be composed of the:
Chairman:
Plant Manager Vice Chairman:
Operations-Maintenance or Technical-Administrative Superintendent Secretary:
Administrative Supervisor Member:
Maintenance Supervisor (I&C) l Member:
Engineering Supervisor Member:
Environmental and Radiation Control Su perv i sor Member:
Quality Assurance Supervisor Member:
Operating Supervisor Member:
Maintenance Supervisor (Mechanical) l ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PtiSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PNSC activities at any one time.
BRUNSWICK-UNIT I 6-6
}
ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PNSC shall meet at least once per calendar nonth and as convened by the PNSC Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the PNSC shall consist of the Chairman or Vice Chairman and three members including alternates.
RESPONSIBILITIES 6.5.1.6 The PNSC shall be responsible for:
a.
Review of 1T all procedures required by Specification 6.3 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect c.uclear safety.
e.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Nuclear Generation and to the Manager - Corporate Nuclear Safety and Quality Assurance Audit.
f.
Review of all events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.
g.
Review of facility operations to-detect potential safety hazards.
h.
Performance of special reviews, investigations and reports thereon as requested by the Manager - Corporate Nuclear Safety and Quality Assurance Audit.
BRUNSWICK-UNIT 1 67 804 007 8
ADMIT 11STRATIVE C0f>TROLS RESP 0tiSIBILITES (Continued) i.
Review of the Plant Security Plan and implementing procedures.
j.
Review of the Emergency Plan and implementing procedures.
AUTHORITY 6.5.1.7 The PfiSC shall:
Recommend to the Plant Manager written approval or disapproval a.
of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed sa fety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the flanager of c.
f;uclear Generation and the fianager - Corporate fluclear Safety and Quality Assurance Audit of disagreement between the PNSC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The Pf;SC shall maintain written minutes of each meeting and copies shall be provided to the Manager of fiuclear Generation and to the Manager - Corporate fluclear Safety and Quality Assurance Audit.
BRUtSWICK-UtlIT 1 68 804
~079
ADMINISTRATIVE CONTROLS 6.5.2 Corporate Nuclear Safety 6 Ouality Assurance Audit Section (CNS 6 OAAS)
Responsibility 6.5.2.1 The Manager - Corporate Nuclear Safety 6 Quality Assurance Audit under the Vice President-System Planning & Coordination is charged with the overall responsibility for administering the independent off-site review and quality assurance audit programs as follows:
Approves selection of the individual (s) to conduct off-a.
site safety reviews and quality assurance audits, b.
lias access to the plant operating records and operating personnel in performing the independent reviews and quality assurance audits.
, Prepares and retains written records of reviews and c.
audits.
d.
Assures independent safety reviews are conducted on all items required by Section 6.5.3.3 and quality assurance audits cover all the items included in Section 6.5.4.1.
Distributes reports and other records to appropriate e.
managers.
6.5.3 Corporate Nuclear Safety Unit 804 080 J. unction BRUNSWICK-UNIT 1 6-9 (Prime)
Effective dates:6/1/79-8/31/79
[
ADMINISTRATIVE CONTROLS 6.5.2 Corporate Nuclear Safety 6 Quality Assurance Audit Section (CNS 6 OAAS)
Responsibility l
t 6.5.2.1 The Manager - Corporate Nuclear Safety 6 Quality Assurance Audit under the Vice President-Nuclear Safety and Research is charged with the overall responsibility for administering the independent off-site review and quality assurance audit programs as follows:
Approves selection of the individual (s) to conduct off-a.
site safety reviews and quality assurance audits.
b.
Has access to the plant operating records and operating personnel in performing the independent reviews cnd quality assurance audits.
__ Prepares and retains written records of reviews and c.
audits.
d.
Assures independent safety reviews are conducted on all items required by Section 6.5.3.3 and quality assurance audits cover all the items included in Section 6.5.4.1.
Distributes reports and other records to appropriate e.
managers.
6.5.3 Corporate Nuclear Safety Unit Function 804 081 BRL'NSWICK-UNIT 1 6-9 Effective date: 9/1/79
ADMINISTRATIVE CONTROLS 6.5.3.1 The Corporate Nuclear Safety tJnit of the Corporate Nuclear Safety & Quality Assurance Audli Section shall provide independent off-site review of significant plant changes, tests, and procedures; verify that reportable occurrences are promptly investigated and corrected in a manner which reduces the probability of recurrence of such events; and detect trends which may not be apparent to a day-to-day observer.
Personnel 6.5.3.2 Personnel assigned responsibility for independent reviews a.
shall be specified in technical disciplines, and shall collec-tively have the experience and competence required to review problems in the following areas:
1.
Nuclear power plant operations 2.
Nuclear engineering 3.
Chemistry and radiochemistry 4.
Metallurgy 5.
Instrumentation and control Radiological safety 7.
Mechanical and electrical engineering 8.
Administrative controls 9.
Seismic and environmental 10.
Quality assurance practices b.
The following minimum experience rcquirements shall be es-stablished for those persons involved in the independent off-site safety review program:
804 082 BRUNSWICK-UNIT 1 6-10
AD'!INISTRATIVE CONTROLS 1.
Manager of CNS & QAAS - Bachelor of Science in engineering or related field and ten (10) years related experience including fiv (5) years involvement with operatio.
and/or design of nuclear power plants.
2.
Reviewers - Bachelor of Science in engineering or related field or equivalent and five (5) 3 ars related experience including three (3) years involvement with operation and/or design of nuclear power plants.
An individual may possess competence in more than one c.
specialty area.
If sufficient expertise is not available within the Corporate Nuclear Safety Unit, competent individuals from other CP&L organizations or outside consultants shall be utiliced in performi q; independent off-site reviews and investigations.
d.
At least tl.cee persons, qualified as discussed in Specifica-tion 6.5.3.2.b, will review each item submi - ed un<'er the requirements of 6.5.3.3.
e Independent safety reviews shall be performed by,)ersonnel not directly involved with the activity or responsible for the activity.
Subj ects Requiring Independent Review 6.5.3.3 The f ollowing subjects shall be reviewed by the Corporate Nuclear Safety Unit:
i 6-11 BRUNSWICK-UNIT 1 i
- 804 083
ADMINISTRATIVE CONTROLS Written safety evaluatio', of changes in the facility as a.
described in the Safety Analysis Report, changes ir procedures as described in the Safety Analysis Report unc tests or e peri-ments not described in the Safety Analysis Repert which are completed without prior NRC appraval Under th ? provisions of 10 CFR 50.59 (a)(1). This review is to verify that such changes.
teste, or experiments did not involve a cha1ge in the techntcal specifications or an unrevi wed safety questioa as defin; in 10 CFR 50.59(a)(2).
b.
Proposed changes in procedures, proposed changes in th_ facility, or proposed tests or experiments, any of which involves a change ir. the technical specifications or n: onreviewed safety ques-tion pursuant to 10 CFR 50.59(c). Matters of this kind shall be referred to the Corporate Nuclear Safety ifait by the Plant Nuclcar Safety Committee following its rev.iew, or by other functional organizational units uithin Carolina Poum. 6 Light Company (CP&L) prior to implementation, Changes in the technical specifications or license amendments c.
relating to nuclear safety prie: to implementation, except in those cases where the change is identical to a previously reviewed proposed change.
d.
Violations, deviations and reportable events, which require reporting to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and as defined in the plant technical specificat i ;as such as:
1.
Violations of applicable codes, regulations, oiders, technical specifications, license requirements or internal procedures or instructions having safety significance; and BRUNSWICK-UNIT 1
~
t
AD:11NISTRATIVE CONTROLS 2.
Significant operating abnormalities or deviations from normal or expected performance of plant safety-related structures, systems, or components.
Review of events covered under this pa.agraph shall include the results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.
Any other matter involving safe operation of the nuclear e.
power plant which the Manager - Corperate Nuclear Saf ety 6 Quality Assurance Audit Section deems appropriate for consideration, or which is referred to the Manager -
Corporate Nuclear Safety & Quality Assurance Audit Section by the onsite operating organization or by other functional organizational units within Carolina Power & Light Company.
Follow-up Action 6.5.3.4 Results 01 Corperate Nuclear Safety (CNS) reviews, including recommendations and concerns will be documented, Copies of the documented review will be retained in the a.
Corporate Nuclear Safety & Quality Assurance Audit Section files.
b.
Recommendations and concerns will be submitted to the tianager-Nuclear Ceneration with 14 days of determination.
A summation of Corporate Nuclear Safety recommendations c.
and concerns will be submitted to the Chairman / Chief Executive
{h BRUNSh'ICK-UNIT 1 6-12a
ADMINISTRATIVE CON 1'ROLS Officer; Chief Operating Officer; Executive Vice President-Power Supply and Customer Services; Senior Vice President-Power Supply; Vice President-System Pla ning & Coordination; Plant Manager; and others, as appropriate on at least a bi-monthly frequency.
6.5.3.5 The Corporate Nuclear Safety Unit review program shall be conducted in accordance with written, approved procedures.
6.5.4 Operation & Msintenance Unit Function 6.5.4.1 The Operation & lbintenance Unit of the Corporate Nuclear Safety & Quality Assurance Audit Section shall perform audits of plant activities.
These audits shall encompass:
The conformance of facility operation to all provisions a.
contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The training and qualifications of the entire facility staff at least once per year.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months.
d.
The verification of compliance and implementation of the requirements of the Quality Assurance Progran to-meet the criteria of Appendix "B", 10 CFR 50, at least once per 804 086 two years.
BRUNSWICK-UNIT 1 6-12b(Prime)
Effective dates:6/1/79-8/31/79
ANTINTSTRATIVE C0hTROLS Officer; Chief Operating Officer; Executive Vice President-Power Supply and Customer Services; Senior Vice President-Power Supply; Vice President-Nuclear Safety and Research; Plant Manager; and others, as appropriate on at least a bi-monthly frequency.
6.5.3.5 The Corporate Nuclear Safety Unit review program shall be conducted in accordance with written, approved procedures.
6.5.4 operation & Maintenance Unit Function 6.5.4.1 The Operation & Maintenance Unit of the Corporate Nuclear Safety & Quality Assurance Audit Section shall perform audits of plant activities.
These audits shall encompass:
The conformance of facility operation to all provisions a.
. contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The training and qualifications of the entire facility staff at least once per year.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months.
d.
The verification of compliance and implementation of the requirements of the Quality Assurance Program tc meet the criteria of Appendix "B", 10 CFR 50, at least once per 804 087 two years.
ERUNSWICK-UNIT 1 6-12b Effective date: 9/1/79
A DMINISTRATIV E CONIROLS
~
e.
Tne Emergency Plan and impi Tenting procecures at least once per two years.
f The Security Plan and implementing procedures at least once per two years.
g.
The Facility Fire Protection Program and implementing procedures at least once per two years.
h.
Any other area of facility operation considered appropriate by the Corporate Quality Assurance Audit Operation 6 Main-tenance Unit, the Executive Vice President-Power Supply and Customer Services, or the Senior Vice President-Power Supply.
Personnel 6.5.4.2 Audit personnel will be independent of the area audited.
a.
Selection for auditing assignments is based on experience or training which establishes that their qualifications are com.nensurate with the complexity or special nature of the ac-
,tivities to be audited.
In selecting auditing persannel, consideration will be given to special abilities, specialized technical training, prior pertinent experience, personal characteristics, and education.
b.
Qualified outside consultants or other individuals independent from those personnel directly involved in plant operation, but within the Operations Groups will be used to augment the audit teams when necessary.
BRUNSWlCK-UNIT 1 6-12c 804, 088
ADf1114ISTRATIVE C0t;TROLS n ports e
6.5.4.3 Results of audit are approved by the Manager - Corporate I;uclear Safety 6 Quality Assurance Audit Section and transmitted directly to the Company Chairman / Chief Executive Officer, the Chief Operating Officer, the Executive Vice President-Power Supply and Customer Services, the Senior Vice President-Power Supply, and the Vice President-System Planning & Coordination, and others as appropriate, within 30 days after the completion of the audit.
6.5.4.4 The corporate quality assurance audit program shal' a
conducted in accordance with written, approved procedures.
6.5.5 0UTSIDE AGEf1CY It!SPECT10ft AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing an outside fire protection firm.
6.5.5.2 An inspection and audit of the fire protection and loss prevention
.(
program shall be performed by a qualified outside fire consultant a-t least once per 36 months.
804 089 BRUNSWICK-Ut1IT 1 6-13 (Prime)
Effective dates:6/1/79-8/31/79
ADMINISTRATIVE CONTROLS reports 6.5.4.3 Results of audit are approved by the Manager - Corporate Nuclear Safety 6 Quality Assurance Audit Section and transmitted directly to the Company Chairman / Chief Executive Officer, the Chief Operating Of ficer, the Executive Vice President-Power Supply and Customer Service.,
the Senior Vice President-Power Supply, and the Vice President-Nuclear Safety and Research, and others as appropriate, within 30 days after the completion of the audit.
6.5.4.4 The corporate quality assurance audit program shall be conducted in accordance with written, approved procedures.
6.5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing an outside fire protection firm.
6.5.5.2 An inspection and aud'^ of the fire protection and loss prevention
{
program shall be performed by a qualified outside fire consultant at least once per 36 months.
BRUNSWICK-UNIT 1 6-13 804 090 Effective date: 9/1/79
ADMIN 5 trail 7E CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
a.
The Commission shall be notifier and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to th9 Commission shall be reviewed by the PNSC and submitted to Manager - Corporate Nuclear Safety and Quality Assur ance Audit and the Manager of Nuclear Generation.
6.7 SACETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
Tne facility shall be placed in at least HOT SHUTDOWN within two hours, b.
The Safety Limit violation shall be reported to the Commission, the Manager Nuclear Generation and to the Manager - Corporate Nuclear Sa fety and Quality Assurance Audit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be preparco.
The report shall be reviewed by the PNSC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon fac ility components, systems or struc-tures, and (3) correctivi cction taken to prevent recurrence, d.
The Safety Limit Violation Report shall be submitted to the Commission, the Manager - Corporate Nuclear 5afety and Quality Assurance Audit and the Manager of Nuclear Generation within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Uritten procedures shall be established, implemented and main-tained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation, f.
Fire Protection Program implementa tion.
%k BRUNSWICK - UNIT 1 6-14
ADMItJISTRATIVE C0tJTROLS RECORD RETEriTI0ri (Continued) h.
Records of annual physical inver.cory of all sealed source material of record.
6.10.2 The following records shall be retained for toe duration of the Facility Operating License:
Records and drawing changes reflecting facility design modifi-a.
cations made to systems and equipment described in the Final Sa fety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
Records of facility radiation anc' contamination surveys.
c.
d.
Records or radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid racioactive material released to the environs, f.
Records of transient or operational cycles for those facility components identi fied in Table 5.7.1-1.
g.
Records of reactor tests anj experiments.
h.
Records of training and qualification for current members of the plant staf f.
i, Records of in-service inspections performed pursuant to these Technical Specifications.
j.
Records of Quality Assurance activities required by the QA Manual.
k.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
)*
Records of meetings of the PNSC and of the previous off-site review organization, Company Nuclear Safety Committee (CNSC).
6.11 RADIATI0tt PROTECTIOil PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintaired and adhered to for all operations involving personnel radiation exposure.
O
! BRUT 45 WICK - UtilT 1 6-20 80
Objective This section describes the administrative controls and procedures necess.ary to implement the Environmental Technical Specifications.
5.1 ORGANIZATIE AND REVIEW The Plant Manager is directly responsible for the safe operation of the facility as shown in Figure 5.1-1(Prime). In all matters pertaining to the
{
operation of the plant and to the Environmental Technical Specifications, the Plant Manager is directly responsible to the Manager of Nuclear Generation.
The Environmental and Radiation Control Supervisor is directly responsible to the Plant Manager for all Environmental Technical Fr.ecifications applicable to the plant, radiological and otherwise.
In the Generatica Department, the Manager - Generation Services, Harris Energy & Environmental Center Section, and his staff function in a staff capacity to assist in the proper implementation of the Environmental Technical Specifications.
Review of plant operations and the technical specifications shall be accomplished by the Plant Nuclear Safety Committee '(PNSC) and the Corporate Nuclear Safety (CMS) Unit as organizationally described in Appendix A to the facility operating license.
Independent off-site QA audits of plant operations shall be performed by the Operation &
Maintenance (0&M) Unit as described in Appendix A to the facility operating license.
Review and audit functions are defined as follows:
Review by PNSC and CNS of proposed changes to the Environmental a.
Technical Specifications and the evaluated impact of the change.
804. 093 BSEP 1 5-1 (Prime) l APPENDIX B Amendment No. M-(o Effective dates: 6/1/79-8/31/79
Obiective This section describes the administrative controls and procedures necessary to implement the Environmental Technical Specifications.
5.1 ORGANIZATION AND REVIEW The Plant Manager is directly responsible for the safe operation of the facility as shown in Figure 5.1-1.
In all matters pertaining to the operation of the plant and to the Environmental Technical Specifications, the Plant Manager is directly responsible to the Manager of Nuclear Cencration.
The Environmental and Radiation Control Supervisor is directly responsible to the Plant Manager for all Environmental Technical Specifications applicable to the plant, radiological and otherwise.
In the Generation Department, the Manager - Generation Services, Harris Energy & Environmental Center Section, and his staff function in a staff capacity to assist in the proper implementation of the Environmental Technical Specifications.
Review of plant operations and the technical specifications shall be accomplished by the Plant Nuclear Safety Committee (PNSC) and the Corporate Nuclear Safety (CNS) Unit as organicationally described in Appendix A to the facility operating license.
Independent off-site QA audits of plant operations shall be performed by the Operation 6 Maintenance (0&M) Unit as described in Appendix A to the facility operating license.
Review and audit functions are defined as follows:
Review by PNSC and CNS of proposed changes to the Environmental a.
Technical Specifications and the evaluated impact of the change.
hk 5-1 APPENDIX B Amendment No. 33:[o BSEP 1 Effective date: 9/1/79
CllAIR.'!AN/CilIEF EXECUTIVE OFFICER OPERATIONS AD;11NISTRATION Senior Executive Vice President President and and Chief Operating Of ficer Chief Administrative Officer
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rp r e Nuclear POW;R SUPPLY AND
- ^ ^"
CUSTOMER FERVICES
.fatters Only g
Executive Vice President g
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P0h'ER SUPPLY
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Senior Vice President
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CORP 0 FATE SERVICES
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Senior Vice President
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GENERATION DEPARTMENT
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Manager
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SYSTE'! PU ;'It;G
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AND
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COORDINATION
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DEPARTME!;T
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Vice President
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GENERATION DEPARTMENT NUCLEAR GENERATION
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staff s
Manager 7
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l CORPORATE NUCLEAR SAFETY
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l_ _ _ _ _
AND QUALITY ASSURANCE AUDIT l
Manager Plant
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f P1 ant Nuclear Safetv Committec
- Responsible for perfornance and monitoring of Fire Protection Progran.
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"A'1AGEMENT ORGA'iIZATIO!i CllART Ficure 5.1-1(Prime)
Et fective dates:
BRUNSk'ICK - UNIT 1
. Tune 1, 1979 - August 31,1979 ppg.g 3
CHAlRMA'i/CllIEF EXECUTIVE OFFICER OPERATIONS Senior Executive Vice President and
[
Chief Operating Officer j
l i
I I
I POWER SUPPLY AND CUSTOMER SERVICES l
Executive Vice President l
l 1
PO'. ER SUPPLY Senior Vice President l
I I
I GENERATION DEPARTMENT NUCLEAR SAFETY l
Manager
.O!D RESEARCH Vice President l
l I
GENERATION DEPARTMENT NUCLEAR GENERATION l
staff s
Manager
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g CORPORATE NUCLEAR SAFETY I
AND
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QUALITY ASSURANCE AUDIT g
Manager Plant y
Manage r i
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Plant Nuclear Safety Co r.:ai t t e e
- Responsible for perforr.ance and monitoring of Fire Protection Program.
h MANAGEMENT ORGANIZATION CHART Figure 5.1-1 BRUNSWICR - UT;IT 1 APPENDIX B
b.
Review by ?NSC and Cis of ch:inges or =cdifica: Cons :=
plan syste=s or ec.uip=en: chid are dece:- d ed by :he Plant P.anager to have a sig-.ifican adverse effec: = the envire==en: and the evaluated i==ac: of the change.
F.aview by ?NSC and Cis of ri::en precedures and changes c.
dere== as described in See:1:n 5.3.2 which are de:er d ed-by the Plan: Manager to de:-i=entally affect the pla=:'s envir===e::a1 i==ac:.
d.
Investiga:ic: by :he ?NSC of reported instances where an envirc:=en:a1 protection id ': is e=ceeded er :he occur-rucce of an : usual envire== ental event associa:ed vi h cperstics of de plan: which i=velves a significan:
- a. viren= ental 1==ac:.
~he reper: and rec._enda:10:s :ha:
result fr:c de ?NSC inves: iga ic: vill be reviewed by the CIS.
Carpers:e q":7 assurance audi: cf plan: cperatices and v-1::en a.
procedures for i=ple=e::a:1:n of these Ce '- d eal Specif1:2:10:s by OMd.
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AL. m.ai. O. 3 e... u-,i
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u PLCT* OPE?.A"'~CNS i.1.1 An env"ren= ental event shall be reported pre==:17 :
the Manager of Nuclear Genera:icn and rev eved by the ?lan: Nuclear Saf ety Co
'::ee.
~he ?lan:
Manager shall take actie c abate a=7 i= ac:,
d ediately following his dece: ' at.:. n of aper:pria:e y
pe==1::ed by de te
'eal specificati =s.
r Fe ac:10:
mm 5.2.2 As specified i: See:1:n 5.l. 2, a reper: of each ri m envirce= ental event shn be reviewed by the ?lan:
h Nuclear Safe:7 Co d::ee.
~his reper: shall include D.s a
an evalua:1 = cf -le cause of :he event, a :scerd of
[
he cor ective actics :aken, and the rec==enda:10:s y
f app cpriate actics :: prevent or reduce ~:
probahd'*:7 of a rect: ence.
en 5-2 Amendments 7
m BSE Appendix B f
- .1.3 Copies of all such* rerorts shan be sub=1
- ted to the Y.anager of Nuclear Genera:10: and :he Manager of Corporate Nuclear Safety and Quality Assurence Audit Section for review.
5.2.4 Ole circu= stances of any envd rennen:a1 even: shall be
- eported :o the NRC as specified i= c ec:ic 5.4.2.
5.3 o?!?.ATT's ??.ccI rRIS 5.3.1
'4ri::en precedures sh= be prepared and approved as specified in Sectie 5.3.2 for opera:ic: :o ensure ce=pliance tri h the envire== ental pretec:10: :: di:1ces and associa:ed su:reillance require =ents of Secticus 2 and 3.
?recedures vill include sa= ling, ar.alysis, and ac:1cus :: be :sken unen environmental p:::ac:ics c edi:1cus are e=ceeded.
Quali:7 assurance precedires will be developed f :===1:cring, sa=cle cellecrian, and sa= 1e analysis.
Testing f equenc7 ef any alar:s will also be included.
5.3.2 Precedures described in See:1c: 5.3.1 abeve, and changes there:c, de:er=ined by the Plan: M.anager :o de:rd en:'7 affect :he plant's e vironnettal i=cac:, shall be reviewed as specified in Sec:10: 5.1 and approved by the ? : Manager prior := i=plementa:ics.
Te==crary changes :: precedures which do not change the intent of the eriginal precedure ca7 be cade, provided such changes are approved by : co ce=ce s of the plaar anagement staff.
Such changes shall be docu-cented, and subsequently rev.eved by the Plan: Nuclear Safe:7 d
Cc d ttee and approved by the ?lan: Manager prior :o i==le-centatice as per=anent proeedure changes.
5.3.2 Precedures desc-ibed in Sectic 5.3.1 abeve, and changes hereto, which are deter =1:ed by _he Pla== Manager to not de: mentally affect the plant 's envire== ental i= pac: shall be reviewed and approved by the ?lan: Manager er c her e=ber of :he plan:
anage=ent staff designated by :he Plan: Manager prior Oc i= le-mentatice.
5.3.1
- J 1::en procedures shall be prepared and approved Q
hf h [f/
h MUY
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d'LO O cIf MMgh BSEP 1 Appendix B 5-3
,xmenCments /