ML20085M784
| ML20085M784 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/22/1991 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085M788 | List: |
| References | |
| NUDOCS 9111120186 | |
| Download: ML20085M784 (33) | |
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UNITED STATES e
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NUCLEAR REGULATORY COMMISSION
- M WASHINGTOfd. D C. 20666 oy
..: y CAROLINA POWER A LIGHT COMPANY, et al.
DOCKET NO. 50-325 RRUNSWICK STEAf1 ELECTRIC PLANT, UNIT 1 AMEPDMENT TO FACILITY OPERt. TING LICENSE 4
Amendment No. 156 License No. OPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for smendment filed by Carolina Power & Light Compny (the licensee), dated January 15, 1991, as supplemented September 30, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as arended (the Act), and the Commission'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 (i) that the activities author-ized by this amendment can be-conducted without endangering the health and safety of it.e public, and (ii) that such activities will be conducted in compliance with the Comis31on's regulations; 1
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 satisfiec'.
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9111120186 911022 L
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2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph P.C.(?) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised throuah Amendment No. 156, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR RFGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor P.egulation
Attachment:
Changes to the Technical Specifications Date cf issuance:
October 22, 1991 1
ATTACHMENT TO LICENSE AMEtIDMENT NO. 156 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-375 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Ir. sert Pages xiv xiv xv xv
- 6. 5 6-5 6-7 6-7 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-25 6-25 i
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INDEX s
ADMINISTRATIVE CC!CECLS s
SECTION EME i
(
6.1 FESPONSIBIL!TY.
61 6.2 CPGANIZATION 6.2.1 OFFSITF AND CNSITE CRGtJIIZATIONS.
61 i
i 6.2.2 FACILITY STAFF.....
61 6.2.3 PROJECT ASSESSMEtC (PA) l runetsen..
6-,
l Responsibilities........
65 Authority..
65 6.2.4 SHIFT TECHNICAL ADVISOR.........
65 f
I
(
6.3 FACILITY STAFF CUALIFICATIQ13
........................... 5 l
6.4
'" RAINING 6-5 6.5 PEVIEW AND AUDIT 6.5.1 ICCLEAR SAFETY REVIEWERS.....
6-6 6.5.2 SAFETY EVALUATICNS AND IlmEPENDE!C REVIEW CONTROL j
Safety Evaluations.
66
[
Procedures, Tests, and Experiments.........
6-7 Modificatiens.
6-7 Operating License / Technical Specifications.............
6-7 6.5.3 PLANT !UCLEAR SAFETY COMMI MEE (PNSC)
- Function, 6-8 Composition..
6-8 Alternates.
68 Meeting Frequency.........
6-8 Querum...........
6-8 Activities...
69 Authority..
6 10 Records..
6-10 BRITNSWICK UNIT 1 XIV Amendment No. 70. I33+
138, 156-i p
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I!CEX C MINISTRATIVE C0!CROLS SECT!2 PAGE 6.5 EEVIEW MiD AUDIT (Continued) 6.5.4 NUCLEAR ASSESSME!C DEPARTME!C I!CEPE!CE!C REVIEW PROGRAM l
Function.,
6-10 Organization.
6-10 Review.
6 11 Records..
6-12 6.5.5 NUCLEAR ASSESEME!C DEPART!EIC AUDIT PROGRAM
{
Function.
6-13 Audits.
6 13 Records.
6 '. 4 Authority.
6-14 Personnel.
6 14 6.5.6 OUTSIDE AGENCY INSPECTICN AND AUDIT PROGRAM...
6-15 6.6 RE?ORTABLE EVENT ACTICN.
6 15 6.
SAFETY LIMIT VIOLATION.
6-15 6.B PFOCEDURES MC PROGPJJG..
6-16 6.9 REPORTING REOUIREME!CS Routine Reports 6 17 Startup Reports.
6-17 Annual Reports.
6-18
?ersonnel Exposure and Mor.itoring Report.
5 18 Annual Radiological Envircnmental Operating Report...
6-19 Semiannual Radioactive Effluent Release Report.
6-20 Monthly Operating Reports.
6-21 Special Reports...
6 22 Core Operating Limits Report..
6- :
4
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BRUNSWICK - UNIT 1 XV Amendment No.
2 fu, 156
QL*INISTRATIVE CONTROLS 6.2.3 PPOJECT ASSESSMEM* (Phl E21.1~rION 6.2.3.1 The PA Group Unit shall function to examine f acility operatir.g l
characteristics, NRC issues, industry advisories, and other sources which may indicate areas for improving facility safety.
EESPONElBILITIES 6.2.3.2 The PA Group Unit shall be responsible for maintaining surveillance
(
of f acility activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.3 The FA Group Unit shall make detailed recommendations for revised l
procedures, equipment modifications, or other means of improving facility safety to the Manager - Nuclear Assessment Departt 1t.
l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor en matters pertaining to the engineering aspects assuring safe cperation of the unit.
6.3 FACILITY STAFF OUALIFICATION 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions (0, except for (1) the Manager Environmental & Radiation Control who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant during transients and accidents, 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Manager Training (BSEP) and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1 1971 and Appendix "A" of 10 CFR Part 55.
' l.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager Training (BSEP) and shall meet or exceed the requirements of Section 27 of the NFPA Code 19 75.
Not responsible for sign-off function.
(a) The requirement for the Manager Operations to hold or have held a senior reactor operator license is exempted for a period of 18 months starting from June 13, 1991.
BRUNSWICK - UNIT 1 6-5 Amendment No. 82. Il3.
153,156 i
l
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AOMINISTP1sTIVE CONTPOLS FFOCEOUREF iSTS. AND EXPERIME!TTS 6.5.2.4 The safety evaluation prepared in accordance with Specificatiens 6.5.2.1.a and 6.5.2.1.b above shall include a written determinatien, with basis, of whether or not the procedures, preposed tests and experiments, and changes thereto constitute an unreviewed safety question e
as defined in 10 CFR 50.59, or whether they involve a change to the Technical Speciticaticas.
6.5.2.5 Following the nuclear safety review, the procedures required tri Specification 6.8, other procedures that affect nuclear safety, proposed tests or experiments, and changes thereto (other than editorial or typographical) which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or change to the Technical Specifications shall be approved prior to implementation by the General Manager - Brunswick Plan
- or his previously designated alternate.
MODIFICATIONS 6.5.2.6 The safety evaluation prepared in accordance with Specification 6.f.2.1.c sbove shall include a written determination, with basis, of whether or not the proposed modification is a change in the facility as described in the safety analysis report, involves a change to the Technical Specifications, or constitutes an unreviewed safety question as defined in 10 CFR 50.59.
6.5.2.7 Following the nuclear safety revies, proposed modifications which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specificativne shall be approved by the General Manager - Brunswick Plant or his previously designsted alternate.
OPERATING I.Im*ENSE/ TECHNICAL SPECIFICATIONS
)
6.5.2.8 The safety evaluation prepared in_accordance with Specifications 6.5.2.1.d and 6.5.2.1.e above shall include a written preliminary determination, with basis, of whether or not the proposed Operating License / Technical Specification change (s) is a change in the facility as described in the safety analysis report.
6.5.2.9 Following the nuclear safety review of the safety evaluation prepared in accordance with Specifications 6.5 2,1.d and 6.5.2.1.e above and the associated proposed action, the request shall be:
Reviewed by the Plant Nuclear Safety Committee in accordance with a.
Specification 6.5.3.B.
b.
Reviewed by the Nuclear Assessment Department Section in accordance l
with Specification 6.5.4.9.
BRUNSWICK - UNIT 1 6-7 Amendment No. 70' A33' 3
156
i r
A0h!'"5 rRATn*E CONTROLS ACTIVITIES 6.5.3.9 The PNSC activities shall include the following:
l Review of all procedures required by Specification 6.8 and changes a.
thereto (and any other procedures and changes thereto), any of which constitute an unreviewed safety question er involve a change to the Technical Specifications, prior to implementation, b.
Review of all preposed tests or experiments that constitute an unreviewed safety questien or involve a change to the Technical l
Specifications, prior to implementation, c.
Review cf all proposed modifications that constitute an unreviewed t
safety question or involve a change to the Technical Specifications, prior to implementation.
d.
Review of all proposed changes to the Technical Specifications or Operating License, prior to implementation, Review of reports on violatiens of Technical Specifications inc*uding e.
reports covering evaluation and reccmmendations to prevent. recurrence to the Manager - Brunswick Nuclear Project and to the Manager -
Nuclear Assessment Department.
f.
Performance of special reviews, investigations (or analyses), and reports thereon as requested by the Manager Nuclear Assessment Department.
g.
Review of all REPORTABLE EVENTS.
l' h
Review of facility operations to detect potential nuclear safety hazards.
i.
Annual review of the Security Plan.
3 Annual review of the Emergency Plan.
k.
Review of accidentcl unplanned, or uncontrolled radioactive release including the preparation of' reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Manager -
Brunswick Nuclear Project and the Manager Nuclear Assassment Department.
1.
Review of changes to the PROCESS CONTROL PROGRA:t and the OFFSITE DOSE CALCULATION MA;TUAL.
BRUNSWICK UNIT 1 6-9 Amendment No.
70, f33, 123, 156 m.m
ICMINISTRA'[T/E CONTPOLS hjn'BCPI'"Y 6.5.3.9 If there is a disagreement between recommendations of a ma3erity of the PNSC and the actions center plated by the General Manager Brunswick Plant, the PNSC shall 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 Manager - Brunswick Nuclear Project and the Vice President - Nuclear Services.
The course determined by the General Manager - Brunswick Plant to be the most conservative shall be follcwed.
EECCFOS 6.5.3.10 The PNSC shall maintain wtitten niinutes of each PNSC meeting that, at a minimum, document the results of all PNSC activities performed under the previsiens of these Technical Specifications.
Copies shall be provided to the Manager Brunswick Nuclear Prc]ect and the Manager Nuclear Assessment Department.
L.5.4.. NUCLEAR ASSESSMENT DEPARTMENT INDEPENDENT REVIEW PROGRAM l
FUNCTION 6.$.4.1 The Nuclear Assessment Department shall function to provide l
independent review of significant plant changes, tests, and procedures; verify that REPORTABLE EVEMS are investigated in a timely manner and correcced in a manner that reduces the probability of recurrence of such events; and detect trends that may not be apparent to a day-to day observer.
QEQhNIZATION 6.5.4.2 The individuals assigned responsibility for independent reviews shall be specified in technical disciplines.
These individuals shall collectively have the experience and competence required to review activities in the following areas; a.
nuclear power plant operations b.
nuclear engineering e.
chemistry and radiochemistry d.
metallurgy e.
non destructive testing f.
instrumentation and control
~
g.
radiological safety h.
mechanical and electrical engineering i,
administrative centrols BRUNSWICK - UNIT 1 6-10 Amendment No.
70, 133, 156
M M!NISTRATIVE CONTPOLS CRGANI* TIC 4 (Continued)
J 3
sea snac and environmental k.
quality assurance practices 1.
Other apprepriate fields associated with the unique characteristics of the nuclear power plant.
6.5.4.3 The Manager Nuclear Assessment Department shall have an academic l
degree in an engineering or related field and, in addition, shall have a minimum of ten years related experience, of which a minimum of five years shall be in the operation and/or design of nuclear power plants.
6.5.4.4 The independent safety review program re*tewers shall have an academic degree in an engineering or related field or equivalent and, in addition, shall have a minimum of five years related experience.
6.5.4.5 An individual may possess competence in more than one specialty area.
If sufficient expertise is not available within the Nuclear Assessment Oepartment, competent individuals from other Carolina Power & Light Company organizations or outsite consultants shall be utilized in performing independent reviews and invescigations.
6.5.4.6 At least three individuals, qualified as discussed in 6.J.4.4 above, shall review each item submitted under the requirements of Section 6.5.4.9.
6.5.4.7 Independent safety reviews shall be performed by individuals not directly involved with the activity under review or responsible for the activity under review.
6.5.4.8 The Nuclear Assessment Department independent safety revisw program l
shall be conducted in accordance with written, approved procedures.
FEVIEW 6.5.4,9 The Nuclear Assessment Department shall perform reviews of the l
following:
a.
The safety evaluations for 1) changes to procedures required by Specification 6.8, 2) modifications of equipment or systems, and
- 3) tests or experiments that constitute a change to the safety analysis report to verify that such actions did not constitute an unreviewed safety question or involve a change to the Technical Specifications.
Implementation may proceed prior to completion of this review.
b.
Proposed changes to procedures required by Specification 6.8, and proposed modifications that constitute an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specifications, prior to implementation.
I BRUNSWICK - UNIT 1 6-11 Amendment No. gJ, f33, 156
I ADMINISTPATIVE COFTROLS
~
~
REVIEW (Continued) c.
Preposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specifications, prior to implementation.
l d.
Preposed changes to the Technical Specifications and Operating
- Lietnse, Violations nf applicable codes, regulations, orders, Technical e.
Specifications, license requirements, and internal procedures or instructions having nuclear safety significance, f.
Significant operating abnormalities or deviations from normal and expected performance of plant safety related structures, systems, or components.
g.
Reportable events.
h.
Reports and minutes of the PNSC.
i.
Any other matter involving safe operation of the nuclear powe
. ian t that the Manager Nuclear Assessment Department deems approp? ate for consideration or which is referred to the Manager - Nuclear Assessment Department by the on-cite operating organization or oth.er functional organizational units within Carolina Power & Light Company.
6.5.4.10 Review of items considered under 6.5.4.9 (e) through (i) above shall include the results of any in'.estigations made and the recommendations resulting from these investigations to prevent or reduce the probability cf recurrence of the event.
i RECCRDS 6.5.4.11 Records of Nuclear Assessment Department reviews, including l
recommendations and concerns, shall be prepared and distributed as indicated below:
Ocpies of documented reviews shall be retained in the Nuclear a.
Assessment Department files, b.
Recommendations and concerns shall be submitted to the General Manager - Brunswick Plant and Manager - Brunswick Nuclear Project, within 14 days of completion of the review.
l A summation of Nuclear Assessment Department's reccmmendations and l
c.
concerns shall be subeitted to the Chairman / President; Executive Vice President Power Supply; Senior Vice President - Nuclear Generation; Vice President - Nuclear Services; Manager Brunswick Nuclear Project; General Manager - Brunswick Plant; and others, appropriate, at least once every two months.
l BRUNSWICr.
UNIT 1 6 12 Amendment No.
- 83. 738, 156
ADMINISTRATIVE CONTROLS
~
6.5.5 NUCLEAR ASSESSMEW DEPAR':HENT AUDIT PROGP.AM l
FUNCTICN 6.5.5.1 The Nuclear Assessment Department shall function to perform audits of l
facility activities specified in Specification 6.5.5.2.
6UDITS 6.5.5.2 Audits of facility activities shall be performed by the Nuclear Assessment Department.
These audits shall encompass:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conw tons at least once per 12 months, b.
The training and qualifications of the entire facility staff at least once per 12 months.
c.
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.
d.
The verificatier of compliance and implementation of the requirements of the Quality Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months.
e.
The Emergency Plan and implementing procedures at least once per 12 months.
f.
The Security Plan and implementing procedures at least once per 12 months.
g.
The Facility Fire Protection Program and implementing procedures at least once per 12 months.
h.
The radiological enviro.. rental monitoring program and the results thereof at least ence per 12 months.
i.
The CFFSITE DOSE CALCULATIONAI, MANUAL and implementing procedures at least once per 24 months.
j.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
BRUNSWICK - UNIT 1 6-13 Amendment No.
73, }J/,
156
AOMINISTRATIVE CO??TROLS A*JDITS (Continued) k.
The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revisien 1, June 1974, and Regulatory Guide 4.1, Revision 1, April 1975, at least once per 12 months.
1.
Any other area of facility cperation considered apprcpriate by the Manager - Nuclear Assessment Department.
l 6.5.5.3 Personnel performing the audits shall have access to the plant operating recorde.
RECORDS 6.5.5.4 Records cf audits shall be prepared and retained.
G.5.5.5 Audit reports encompassed by 6.5.5.2 above shall be prepared, approved by the Manager - Nuclear Assessment Department, and ferwarded to the l
Executive Vice President Power Supply; Senior Vice President Nuclear Generation; Manager - Brunswick Nuclear Project; General Manager + Brunswick Plant; and others, as apprcpriate, within 30 days af ter completion of the audit.
AUTHORI'"Y 6.5.5.6 The Manager - Nuclear Assessment Department shall be responsible for l
the following:
The administering of the Nuclear Assessment Department Audit Program.
I a.
1 b.
The approval of the individual (s) selected to conduct audits.
l PEPSONNEI 6.5.5.7 Audit personnel shall be independent of the area audited.
6.5.5.8 Selection of personnel for auditing assignments shall be based on experience or training that establishes that their qualifications are commensurate with the complexity or special nature of the activities to be audited.
In selecting-audit personnel, consideration shall be given to special abilities, specialized technical training, prior pertinent experience, personal characteristics, and education.
6.5.5.9 Qualified outside consultants or other individuals independent from those personnel directly involved in plant operation shall be used to augment the audit teams when necessary.
I BRUNSWICK - UNIT 1 6-14 Amendment No.
- 83. I38, 156.
f AOMINISTRATIVE COFTROLS i
6.5.6 CUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.6.1 An independent fire protection and loss pret..,: ion inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel er an outside fire protection firm.
6.5.6.2 An inspection and audit of the fire protection and loss preventAon program shall be performed by an outside qualified fire consultant at intervals no greater than 36 menths.
W REPORTABLE EVENT AC"' ION 6.6.1 The f ollowing actions shall be taken for REPO"'."GLE EVENTS:
a.
The Commission shall be notified and a reporc submitted pursuant to the requirements of Secticn 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Plant Nuclear Safety Committee Brunswick Plant and shall be submitted to the Pa ager -
Nuclear Assessment Department and the Manager - Brunswick Nuclear Project.
G.7 SAFE'IT 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 NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Manager - Brunswick l
Nuclear Project and the Manager - Nuclear Assessment Department shall l
j be notified 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 Violatien Report shall be prepared. The report shall be reviewed by the General Manager - Brunswic) Plant.
This report shall describe (1) applicable circumstances preceding the violation, (2) ef fects of the violation upon facilit.y components, systems, or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the Mtnager - Brunswick Nuclear Project, and the Manager -
i Nuclear Assessment Department within 14 days of the violation.
l BRUNSWICK - UNIT 1 6 15 Amendment No. 83, 138, 156
ADMINISTPATI'.*E CONTROLS PECOROS RETEN"' ION (Continued) k.
Records of reviews perf omed f or changes made to procedures or e qu:,pment or reviews of tests and experiments pursuant to 10 CFR 50.59.
1.
Records of the service lives of all hydraulic and mechanical snubbers referenced in Section 3.7.5 including the data at which the service life commences and aerociated installation and maintenance records.
Records of analyses required by the radiological envirenmental m.
monitoring program.
n.
Records of (1) meetings of the PNSC, (2) meetings of tae previous off-site review organization, the Company Nuclear Safety Committee (CNSC),
(3) the independent reviews perfomeu by the Nuclear Assessment Department, and (4) the independent reviews perfomed by the Corporate Quality Assurance Audit Program, Quality Assurance Auditing Unit.
6.11 RADIATION PROTEC"' ION PROGPAM 6.11.1 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.
6.12 HIGH PADIATION AREA 6.12.1 In lieu of the " Control Device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem /hr or less 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)*
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
BRUNSWICK UNIT 1 6 25 Amendment No. 83. I3I+
- T38, 156
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION 5
- D[ff o,
WASHINoToN. D.C. 20656
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CAROLINA POWER & LIGHT COMPANY, et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLAtlT, UNIT ?
AMENDMENT TO FACILITY OPERATING LICENSE Amendment' flo.
187 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated January 15, 1991, as supplemented September 30, 1991, complies with the standards ~and requirements of the Atomic Energy Act of'1954, as amended (the Act) and the Commission'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 author-ized by this amendntent can be conducted without endangering the health and safety of. the public, and (ii) that such activities will be conducted in compliance with-tha 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-accordance with.10 CFR' Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
lI
.p.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of facility Operating License No. DPR-62 is hereby amended to read as follows:
(2) Tect 11 cal Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment bo. 187, are hereby incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordancc v;ith the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 22, 1991 l
l r
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l ATIACHMENT TD LICENSE AMENDMENT NO.
187 FACILITY OPERt. TING i.ICENSE NO. nPR-6?
DOCKET NO. E0-3?4 Replace the following pages of the Appendix A Technical Specifications with the enclossd pages., The revised areas are indicated by marginal lines.
Remove Pag g Insert Pages xiv xiv xv xv 6-5 6-5 6-7 6-7 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-D 0 25 M-
INDEX AOMINISTPATIVE CO!T 'ROLS SECTICN PAqg 6.1 P"SPONSIBILI~'Y...
6-1 6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS..
6-1 6.2.2 FACILITY STAFF..
6-1 6,I.3 PROJECT ASSESSMENT (PA) l Function...
6-5 Responsibilities..
6-5 Authority..
6-5 6.I.4 SHIFT TECHNICA!. ADVISOR.
6-5 6.3 FACILITY STAFF OUALIFICATICN.,
6-5 6.4 TRAINING........
6-5 6mS REVIEW AND AUDIT 6.5.1 NUCLEAR SAFETY REVIE*n*ERS....
6-6 6.5.2 SAFETY EVALUATICNS AND INDEPENDENT REVIi:M CONTROL Safety Esaluations....
6-6 Procedures, Tests, and Experiments.
67 Modificaticns.
6-7 Operating License / Technical Specifiestiens.
6-7 6.5.3 PLANT NUCLEAR SAFETY COMMITrEE (PNSC)
Function.
6-8 Composition.
6-8 Alternates..
6-8 Meeting Frequency...
6-8 Quorum.,
6-8 Activities.....
6-9 Authority.. 10 Records....
5-10 U
BRUNSWICK
"' T 2 XIV Amendment No. gg,-yg3 170, 187
ItCEX ADMINISTRATIVE CONTPOLS SECTION PAGE 6.5 REVIEW AND AUDIT (Continued) 6.5.4 NUCLEAR ASSESSMENT DEPARTMENT INDEPENDENT REVIEW PROGRAM l
Function.
6-10 Organization.....
6 10 Review.
6-11 Records.
6-12 6.5.5 NUCLEAR ASSESSMENT DEPARTMENT AUDIT PROGRAM l'
runction.
6-u Audits.
6-13 Records.
6-14 Authority.
6-14 Personnel.
6-14 6.5.6 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM....
6-15 6.6 REPORTABLE EVEN" ACTION.
6 15 6. '7 SAFETY LIMIT VTOLATION.
6-15 6 8 PROCEDURES AND PROGRAMS...
6-16 6.9 REPORTING REOUIREMENTS Routine Reports 6-17 Startup Reports....
6-17 Jm ual Reports.
6-18 Personnel Exposure and Monitoring Report.......
6-18 Annual Radiological Environmental Operating Report....
6-19 Semiannual Radioactive Effluent Release Report........
6-20 Monthly Operating Reports.......................
6-21 Special Reports.........
6-22 Core Operating Limits Rs. port.
6 22 1
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~ BRUNSWICK - UNIT 2 XV Amendment No. 170, 763 170, 187 1
-._,1
-._.r.
,.~e,
ADMINISTRATIVE CONTPOLS i
6.2.3 PROJEC* ASSESSMENT fPA) l FUNCTION 6.2.3.1 The PA Group Unit shall tunction to examine facility operating characteristics, NRC issues, industry advisories, and other sources which may indicate areas for improving facility safety.
RESPONSIBILITIES 6.2.3.2 The PA Group Unit shall be responsible for maintaining surveillance l
of facility activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
I THORI*Y 6.2.3.3 The PA Group Unit shall make detailed recommendations for revised I
procedures, equipment modifications, or other means of improving facility safety to the Manager - Nuclear Assessment Department.
l L2. 4 SHIP'" TECHNICAL ADVISCR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shif: Supervisor en matters pertaining to the engineering aspects assuring safe cperation of the unit.
6.3 FACILITY STAFF OUALIFTCATION 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1973 for comparable positions (a) except for (1) the Manager - Environmental & Radiation Control who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant during transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Manager - Training (BSEP) and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 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 Manager - Training (BSEP) and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
l Not responsible for sign-off functien.
(a) The requirement f or the Manager - Operations to hold or have held a senior-reactor operator license is exempted for a period of 18 months starting from June 13, 1991.
BRUNSWICK - UNIT 2 65 Amendaent No.
ffg, 17@
123, 187
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AOMINISTRATIVE CONTROLS i
PROCEDURES. TESTS. AND EXPERIMENTS 6.5.2.4 The safety evaluation prepared in accordance with Specifications 6.5.2.1.a and 6.5.2.1.b above shall include a written I
de t e rminati on, with basis, of whether or not the procedures, proposed tests and experiments, and changes thereto constitute an unreviewed safety question as defined in 10 CFR 50.59, or whether they involve a change to the Technical Specifications, 6.5.2.5 Following the nuclear safety review, the procedures required by Specificatien 6.8, other procedures that affect nuclear safety, proposed tests vr experiments, and changes thereto (other than editorial or typographical) which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or change to the Technical Specifications shall be approved prior to implementation by the General Manager - Brunswick Plant or his previously designated alternate.
MODIFICATIONS 6.5.2.6 The safety evaluation prepared in accordance with Specification 6.5.2.1.c above shall include a written determination, with basis, of whether er not the prcposed modification is a change in the facility as described in the ssfety analysis report, involves a enange to the Technical Specifications, or constitutes an unreviewed safety question as defined in 10 CFR 50.59.
6.5.2.7 Following the nuclear safety review, propcsed modifications which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specificatirns shs11 be approved i
by the General Manager - Brunswick Plant or his previo-.ly des ;nated al te rnate.
OPEFATING LICENSE /TECFl!! CAL SPECIFICATIONF 6.5.2.8 The safety evaluation prepared in accordance with Specifications 6.5.2.1.d and 6.5.2.1.e abeve shall include a written l
preliminary determination, with basis, of whether or not the proposed Operating License / Technical Specification change (s) is a change in the facility as described in the safety analysis report.
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6.5.2.9 Following the nuclear safety review of the safety evaluation prepared in accordance with Specifications 6.5.2.1.d and 6.5.2.1.e above and the associated proposed action, the request shall be:
j Reviewsd by the Plant Nuclear Safety Committee in accordance with a.
l Specification 6.5.3.8.
b.
Reviewed by the Nuclear Assessment Department Section in accordance
{
with Specification 6.5.4.9.
BRUNSWICK - UNIT 2 67 Amendment No. 98, 770 187
AOMINISTRATIVE CONTROLS AC"'IVITIE S 6.5.3.8 The PNSC activities shall include the fcllowing:
a.
Review of all procedures required by Specification 6.8 and changes thereto (and any other procedures and changes thereto), any of which constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
b.
Review of all proposed tests or experiments that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation, c.
Review of all proposed modifications that constitute an unreviewed safety question or involve a change to the Technical Specifications, prier to implementation.
d.
Review of all proposed changes to the Technical Specificatiens or Operating License, prior to implementation.
Review of reports on violations of Technical Specifications including e.
reports ccvering evaluation and rec-Mations to prevent recurrence to the Manager - Brunswick Nuclear Project and to the Manager -
i Nuclear Assessment Department.
l l
f.
Performance of special reviews, investigations (or analyses), and reports thereon as requested by the Manager Nuclear Assessment Department.
q.
Review of all REPORTABLE EVENTS.
h.
Review of f acility operations to detect potential nuclear safety
- hazards, i.
Annual review of the Security Plan.
j, Annual review of the Emergency Plan.
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k.
Review of accidental, unplanned, or uncontrolled radioactive release l
including the preparation cf reports covering evaluation, l
recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Manager -
Brunswick Nuclear Project and the Manager - Nuclear Assessment Department.
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1.
Review of changes to the PROC 2SS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
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BRUNSWICK - UNIT 2 6-9 Amendment No.
II0+ I7Ni 187
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ADMINISTPATIVE CO!CROLS AUTHORITY 6.5.3.9 If there is a disagreement between recommendations of a majority of the PNSC and the actions contemplated by the General Manager - Brunswick Plant, the PNSC shall 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 Manager - Brunswick Nuclear Project and the Vice President - Nuclear Services.
The course determined by the General Manager - Brunswick Plant to be the most conservative shall be followed.
FECCRDS l
6.5.3.10 The PNSC shall maintain written minutes of each PNSC meeting that, at a minimum, document the results of all PNSC activities performed under the l
provisions of *1ese Technical Specificaticns. Copies shall be provided to the Manager - Brunswick Nuclear Project and the Manager - Nuclear Assessment Department.
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6.5.4 NUCLEAR ASSLSSMENT DEPARTME!C INDEPENDENT REVIEW PROGRAM l
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N!C ION 6.5.4.1 The Nuclear Assessment Department chall function to provide l
l independent review of significant plant changes, tests, and procedures; verify that REPORTABLE EVENTS are investigated in a timely manner and corrected'in'a manner that reduces the probability of recurrence of such events; and detect t
trends that may not be apparent to a day to-day observer.
OPGANIZATION 6.5.4.2 The individuals assigned responsibility for independent reviews shall be specified in technical disciplines. These individuals shall collectively have the experience and competence required to review activities in the following areas:
a.
nuclear power plant operations b.
nuclear engineering c
chemistry and radiochemistry d.
metallurgy e.
non destructive testing l
j f.
instrumentation and control g.
radiological safety h.
mechanical and electrical engineering 1.
administrative controls 4
i BRUNSWICK - UNIT 2 6-10 Amendment No.
772, I7@,
187
~,
e n-
AOMINISTEATI"E COi4TROLS ORGA'iI".ATION (Continued)
].
seismic and environmental I
k.
quality assurance practices 1.
Other appropriate fields associated with the unique chsracteristics of the nuclear power planc.
6.5.4.3 The Manager - Nuclear Assessment Department shall have an academic l
degree in an engineering or related field and, in addition, shall have a minimum of ten years related experience, of which a minimum of five years shall be in the operation and/or design of nuclear power plants.
6.5.4.4 The independent safety review program reviewers shall have an academic degree in an engineering or related field or equivalent and, in addition, shall have a minimum of five years related experience.
6.5.4.5 An individual may possess competence in more than one specialty area.
If sufficient expertise is not available within the Nuclear Assessment Department, competent individuals from other Carolina Power & Light Company organizatiens or curside consultants shall be utilized in perfomning independent reviews and investigations.
6.5.4.6 At least three individuals, qualified as discussed in 6.5.4.4 above, shall review each item submitted under the requirements of Section 6.5.4.9.
6.5.4.7 Independent safety reviews shall be performed by individuals not directly involved with the activity under review or responsible for the activity under review.
6.5.4.8 The Nuclear Assessment Department independent safety review program l
shall be conducted in accordance with written, approved procedures.
P E'.'IEW 6.5.4.9 The Nuclear Assessmant Department shall perform reviews of the l
following:
a.
The safety evaluations for 1) changes to procedures required by Specification J.8, 2) modifications of equipment or systems, and
- 3) tests or experiments that constitute a change to the safety analysis report to verify that such actions did not constitute an l
unreviewed safety question or involve a change to the Technical Specifications.
Implementation may proceed prior to completion of this review, b.
Preposed changes to procedures required by Specification 6.8, and proposed modifications that constitute an unreviewed safety question as defined in 10 TTR 50.59 or a change to the Technical Specifications, prior to implementation.
BRUNSWICK - UNIT 2 6 11 Amendment No.
IIO, I70.
187
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ADMINISTPATIVE CCW"*FOLS 4
PEVIEW (Continued) c.
Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical l
Specifications, prior to implementation, d.
Proposed changes to the Technical Specifications and Operating
- License, e.
Violations of applicable codes, regulations, orders, Technical Specifications, license requirements, and internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnomalities or deviations from nomal and expected performance of plant safety-related structures, systems, or components.
g.
Reportable events.
h.
Reports and minutes of the PNSC.
i.
Any other matter involving safe operation of the nuclear power plant that the Manager - Nuclear Assessment Department deems appropriate for consideration or which is referred to the Manager - Nuclear Assessment Department by the on site operating organization or other functional organizaticnal units within Carolina Power & Light Company.
6.5.4.10 Review of items considered under 6.5.4.9 (e) through (i) above shall include the results of any investigations made and the recommendations resulting from these investigations to prevent or reduce the probability of recurrence of the event.
RECCROS 6.5.4.11 Reccrds of Nuclear Assessment Department reviews, including l
recommendations and concerns, shall be prepared and distributed as indicated below:
a.
Copies of documented reviews shall be retained in the Nuclear Assessment Departmeut files, b.
Recommendations and concerns shall be submitted to the General Manar;r - Brunswick Plant and Manag0r - Brunswick Nuclear Pro]ect, withis: 14 days of completion of the review.
c.
- f. summation of Nuclear Assessment Department's recommendations and l
concerns shall be submitted to the Chaiman/ President; Executive Vice President - Power Supply; Senior Vice President - Nuclear Generation; Vice President - Nuclear Services; Manager - Brunswick Nuclear Pro]ect; General Manager - Brur.swick Plant; and others, appropriate, at least once every two months.
BRUNSWICK UNIT 2 6-12 Amendment No.
110, 170 187 n..
ADMINISTRATIVE CO!CPOLS E.5.5 NUCLEAR ASSESSME!C OEPARMNT AUDIT PROGPAM
{
FU!CION 6.5.5.1 The Nuclear Assessment Department shall f unction to perform audits of l
facility activities specified in Specification 6.5.5.2.
AUDITS 6.5.5.2 Audits of f acility activities shall be performed by the Nuclear Assessment Department.
These audits shall encompass:
The conformance of facility operation to provisions contained within a.
the Technical Specifications and applicable license conditions at least once per 12 months.
b b.
The training and qualifications of the untire facility staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in c.
facility equipment, structures, systems, or methods of operat?.on that affect nuclear safety at least once per 6 months.
d.
The verification of compliance and implementation of the requirements of the Quality Assurance Program to meet the criteria of Appendix "B",
1C CFR 50, at least once per 24 months, The Emergency Plan and implementing procedures at least once per 12 e.
months.
f.
The Security Plan and implementing procedures at least once per 12
- months, g.
The Facility Fire Protection Program and implementing procedures at least once per 12 months, h.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
The OFFSITE DOSE CALCULATIONAL MANUAL and implementing procedures at 1.
least once per 24 months.
The PROCESS CONTEOL FROGRAM and implementing procedures for processing 3
and packaging of radioactive wastes at least once per 24 months.
BRUNSWICK - UNIT 2 6-13 Amendment. No.
gg, y7g 187
ADMINISTRATIVE CONTROLS AUDITS (Continued) k.
The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974, and Regulatory Guide 4.1, Revision 1, April 1975, at least once per 12 months.
1.
Any other area of f acility operation considered appropriate by the Manager Nuclear Assessment Department.
l 6.5.5.3 Personnel performing the audits shall have access to the plant operating records.
RECCP.DS 6.5.5.4 Reccrds of audits shall be prepared and retained.
6.5.5.5 Audit reports encompassed by 6.5.5.2 above shall be prepared, approved by the Manager - Nuclear Assessment Department, and forwarded to the l
Executive Vice President - Power Supply; Senior Vice President - Nuclear Generation; Manager Brunswick Nuclear Project; Generel Manager Brunswick Plant; and others, as appropriate. within 30 days after completico of the audit.
AUTHORITY 6.5.5.6 The Manager - Nuclear Assessment Department shall be responsible for the following:
The administering of the Nuclear Assessment Department Audit Program.
l a.
b.
The approval of the individual (s) selected to conduct audits.
l PERSONNEL 6.5.5.7 Audit personnel shall be independent of the area audited.
6.5.5.8 Selection of personnel for auditing assignments shall be based on experience or training that establishes that their qualifications are commensurate with the complexity cr special nature of the activities to be audited.
In selecting audit personnel, consideration shall be given to special abilities, specialized technical training, prior pertinent experience, persenal characteristics, and education.
6.5.5.9 Qualified outside consultants or other individuals independent from those personnel directly involved in plant operation shall be used to augment the audit teams when necessary.
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BRUNSWICK - UNIT 2 6-14 Amendment No.
770, 170
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187
ADMINISTRATIVE C074TROLS 6.5.6 OUTSIDE AGENCY INSPEC'* ION kND AUDIT PRCGRAM 6.5.6.1 An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either l
qualified of f site licensee personnel or an outside fire protaction fim.
l 6.5.6.2 An inspectien and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months.
6.6 REPORTABLE EVEfC ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVEICS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.'3 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Plant Nuclear Safety Co::nittee - Brunswick Plant and shall be submitted to the Mariager -
Nuclear Assessment Department and the Manager - Brunswick Nuclear Project.
6.'
SAFETY LIMIT VIOLATIQ11 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
'"he f acility shall be placed in at least HOT SHL'I'DOWN within two hours.
b.
The NRC Operatiens Center shall be notified by telephone as soon as possible and in all cases within one hour. The Maaager Brunswick Nuclear Project and the Manager --Nuclear Assessment Department shall l
be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Lir-it Violation Report shall be prepared. The report shall be reviewed by the General Manager - Brunswick Plant.
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.
d.
The Safety Limit Violatifn Report shall be submitted to the Commission, the Manager - Brunswick Nuclear Project, and the Manager -
Nuclear Assessment Department within 14 days of the violation.
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l BRUNSWICK - UNIT 2 6 15 Amendment No.
179, 770 187 l
.A...
ADMINISTRATIW CCNTROI.S 4
RECORDS RETEm' ION (Continued) k.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50 59.
1.
Records of the service lives of all hydraulic and mechanical snubbers referenced in Section 3.7.5 including the data at which the service life commences and associated installation and maintenance records, Records of analyses required by the radiological environmental m.
monitoring program.
n.
Records of (1) meetings of the PNSC, (2) meetings of the previous off-site review crganization, the Company Nuclear Safety Committee (CNSC),
(3) the independent reviews performed by the Nuclear Assessment Department, and (4) the independent rev;ews performed by the Corporate Quality Assurance Audit Program, Quality Assurance Auditing Unit.
6.11 RADIATION PROTECTICS PROGPR4 6.11.1 Procedures for personnel radiation protection shall be prepared k
consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and ac hered to for all operations involving personnel radiation a
exposure.
6.12 HIGH RADIATION APIA 6.12.1 In lieu of the " Control Device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 2000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be cont::ciled by requiring issuance of a Radiation Work Permit (RWP)*.
Any individual or group of individuals permitted to enter such areas shall b3 provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area, b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such a.eas with this monitoring devict may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt frem the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they co= ply with approved radiation protection procedures for entry into high radiation r.reas.
BRUNSWICK UNIT 2 6-25 Amendment No.
770, 167, 170, 187 I
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