ML20066F449
| ML20066F449 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/15/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20066F441 | List: |
| References | |
| NUDOCS 9101230338 | |
| Download: ML20066F449 (26) | |
Text
. _
ENCIDSURE 4 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS $c.325 6 50 324 OPERATINC LICENSES DPR 71 6 DPR.62 REQUEST FOR LICENSE AMENDMENT NUCLEAR ASSESSMENT DEPARTMENT ORCAN12ATION CilANCES TECilNICAL SPECI*ICATION PAGES. UNIT 1 i
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i 9101230338 910115
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i INDEX
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ADMINISTRATIVE CONTROLS s
i SECTION PACE J
1 6.1 RESPONSIBILITY............................................
6-1 a
i 6.2 ORCANIZATION I
6.2.1
'0FFSITE AND ONS!it 0RCANIZATIONS.......................-
6-1 l'
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6.2.2 FACILITY STAFF.........................................
6-1
...m. M. s.ML., C PA) f1 91 M T... h S).L U 6.2.3 1
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Function...............................................
6-$
l Responsib(11tles.......................................
6-5 Authority..............................................
6-$
6.2.4 8HIFT TECHNICAL-ADVISOR................................
6-$
J 6.3 FACILITY STAFF QUALIFICATION................................
6-5 6_. 4 TRAIN!NC...................................................:
6 A 6.5 REVIEW AND AUD_I_T 4
j 6.5.1 NUCLEAR SAFETY REVIEWERS...............................
6-6 6.5.2 SAFETY EVALUATIONS AND INDEPENDENT-REVIEW CONTROL Safety Evaluations.....................................
6-6 Proc ec'9te s, Te s t s, and Expe r iment s.....................
- 6-7 I
Modifications..........................................
6-7 operating License / Technical Specifications.............-
6 - 7_.
6.5.3 PLANT NUCLEAR SAFETY COMMITTEE'(PNSC) i Function...............................................
6-8 Composition............................................-
6-8 Alternates..................
4.........................
6-8 Meeting Frequency................
....................L 6-8 Quorum.................................................-
6-8' Activities.............................................'
6 '
Authority..............................................
6-10 Records................................................
6,
BRUNSWICK - UNIT.1 XIV Amendment No. 138 h
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INDEX s
i ADMINISTRATIVE CONTROLS E
I SECTION PACE 6.5 REVIEW AND AUDIT (Continued)
- .acg:12,: gp:L:'{NT pp;;ARNE.NT wt>(PENDENT REVitN PROGRW N
AIL A sM 6.5.4
- A..
- ^r Function...............................................
6-10 Organization...........................................
6 Review.................................................
6-11 Records................................................
6-12 NMyt ASBESGMENT ptPARTMENT i
6.$.$
__.__2;" ^UAL:77 A;.U12%. AUDIT PROGRAM Function...............................................
6-13 Audits.......................................
6-13 Records................................................
6-14 Authority...............................................
6-14 Personne1..............................................
6-14 6.5.6 0UTSIDE ACENCY INSPECTION AND AUDIT PROGRAM............
6-15
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6.6 REFORTABLE EVENT ACTION....................................
6-15 1
6.7 SAFETY LIMIT VIOLAT!0N.....................................
6-15 6.8 PROCEDURES AND PR0 CRAMS....................................
6-16 i
6.9 REPORTINC REQUIREMENTS 3
Routine Reports.......................................
6-17 Startup Reports........................................
.6-17 Annual Reports.........................................
6-18 Personnel Exposure and Monitoring Report.........~......
6-18 Annual Radiological Environmental Operating-Report.....
6-19 Sealannual Radioactive Effluent Release R& port.........
6-20 i
Monthly Operating Reports..............................
6-21 i
Special Reports........................................
6-22 i
Core Operating Limits Report...........................
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BRUNSWICK - UNIT 1 XV
. Amendment No. 138
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l ADMIN!STRATIVE CONTROLS
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PROJECT A 55E DME PJ T, (PA,)
i 6.2.3 CNS:TE NUO' CA 0 A."ETY '^MC,
i FUNCTION PA G 6.2.3.1 The 0 0 1. reg. shall function to examine facility operating characteristics, NRC issues, industry advisories, and other sources which may indicate areas for. Improving facility safety.
RESPONSIBILITIES j
TheOb shall be responsible for maintaining survelliance of-6.2.3.2 facility activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
1 AUTHORITY fA GW 6.2.3.3 The OG 1.i; shall make detailed recommendations for revised procedures, equipment modifications, or other means of improvlng facility safety to the Manager g ; ;
- i;f.
- .; ; ;f 6.2.4
$HIFT TECHNICAL ADVISOR i
l 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to l
the Shift Operating Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
i 6.3 FACILITY STAFF QUA!.1FICATION j
6.3.1 Each member of the facility stc ! shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the 1
Hanager - 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 i
l 6.4.1 A retraining and replacement training program for the fac'ility staff l
shall be maintained under the direction of the Manager - Training (BSEP) and 1
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.
~j 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.
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- Not responsible for sign-off function.
1 BRUNSWICK - UNIT 1 6-5 Amendment No.=13'l
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ADMINISTRATIVE CONTROLS PROCEDURES, TESTS, AND EXPERIMENTS l
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-determination, 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 Po11owing the nuclear safety review,.the procedures-required by Specification 6.8, other procedures that affect nuclear safety, proposed tests or experiments, and changes thereto-(other, than editorial or typographical) j which hs,ve been determined to not involve an unreviewed-safety question as; r
defined in 10 CFR 50.59 or change'to the Technical Specifications shall be i
appr.rved prior to implementation by.the General Manager - Brunswick Plant or-his previously designated-alternate.'
H00!FICATIONS I
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6.3.2.6 The safety evaluation prepared in accordance with
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Sp.1cif f :stion 6.5.2.1.c above shall. Include a written determination, with' a
ba11s, of whether or not, the proposed modification is a change in the f acility 1
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 50.39.
i 6.522.7 Following the nuclear safety. review,' proposed modifications ~whihh' have been determined to not involve an unreviewed safety question as. defined in 10 CPR 50.59 or a change to the Technical Specifications shall be approved by the General Manager - Brunswick' Plant-or his previously designated-alternate.
OPERATING LICENSE / 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 safet/ evaluation prepared in accordance.with Specifications 6.5.2.1.dcand 6.5.2.1.e above and'the associated proposed action, the requestLshall bet s.
Reviewed by the_ Plant Nuclear Safety Committee in accordance with Specification 6.5.3.8.
Reviewed by the :ucleew AssessmerA. Depp:rimerk N
b.
g;. = 5x h n R f::7. n ;;.in accordance with Specification 6.5.4.9.
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l BRUNSWICK - UNIT 1-6-7
. Amendment No'. 138
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ADMINISTRATIVE CONTROLS ACTIVITIES 6.5.3.8 The PNSC activities shall include the followingt.
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 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 Spectiications, prior to. irtplementation.
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c.
Reviev of all proposed modifications that constitute'an unreviewed safety question or_ involve a change to the Technical Specifications, prior to implementation.
1 d.
Review of all proposed changes to.the Technical Specifications or Operating License, prior to implementation.
-j Review of reports on violations of Technical Specifications including e.
i reports covering evaluation and recommendations to prevent recurrenen i
to the Manager - Brunswick Nuclear Project and to the Manager -
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0;.e::::: 5' :1::: S:!:t; ? :t! - Muciane Assessment Departmenk.
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Performance of special reviews, investigations (or analyses), and reports thereon as requested by the Manager - 0::;::::: " :1::e i
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. NucAcar Assessmenk Deparkmank.
g.
Review of all REPORTABLE EVENTS.
I h.
Review of facility operations to detect potential nuclear safety hazards.
i.
Annual review of the Security Plan.
J.
Annual review of the Emergency Plan.
k.
Review of accidental, unplanned, or uncontrolled radioactive release.
including the preparation of reports covering evaluation, recomendations and disposition of 'the corrective action to prevent' recurrence and the forwarding of these reports to the Manager -
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Brunswick Nuclear Project and the Manager - C;.p;.et; "_:1;;; C f;;y Beet 4em Nuc3ene Assessmank Deparkme.nt.
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
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BRUNSWICK - UNIT 1
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6-9' Amendment No. 138 l
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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.3.9 If there is a disagreement between recommendations of a majority of the
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PNSC and the actions contemplated by the General Manager - Brunswick Plant, the PNSC shall provide written notificalion 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.
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RECORDS i
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_
provisions of these Technical Specifications. Copies shall be provided to the I
Manager - Brunswick Nuclear Project and the Manager
"= p = : "=1:n S:!:t-j mia. Nucleosr Assessment Department.
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I 6.5.4 5
FUNCTION f
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hpnt=.: shall function to provide independent review of significant plant
- changes, tests, and procedurest verify that REPORTABLE EVENTS are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such eventst and detect trends that may not be apparent to a day-to-3 day observer.
ORCANIZATION h
q 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 areast' a.
nuclear power plant operations l
l b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy l
e.
non-destructive testing f.
instrumentation and control g.
. radiological safety h.
mechanical and electrical engineering i.
administrative controls BRUNSWICK - UNIT 1 6-10 Amendment No.'138 l
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ADMINISTRATIVE CONTROLS ORCANIZATION (Continued) j.
seismic and environmental
.i k.
quality assurance practices 1.
Other appropriate fields associated with the. unique characteristics I
of the nuclear power plant.
Nucitar Assessment Department i
6.5.4.3 The Manager 3 m re a n L d ;;; 0;f;O 0;;;i:. shall have an academic 0
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.
Nuclear Assessment Deoartment.
6.5.4.5 An individual may possess ' competence in more than one s'pecialty -
area.
If sufficient expertise is not available within the cc:peret: M:1:::
0;f :y S:::i:n, competent individuals from other Carolina Power & Light Company organizations or outside consultants shall be utilized in performing independent reviews and investigations.
i 6.5.4.6 At least three individuals, qualified as discussed in 6.5.4.4 above, i
shall review each item submitwed under the requirements of Section 6.5.4.9.
l 6.5.4.7 Independent safety reviews shall be performed by individuals not directly involved with the ac*ivity under review or responsible for the
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activity under review.
l The 0;;;;;;;; Sd ;r 0;f;parkenent Nuc\\ ear Assessment De 6.5.4.8
- y 0;; tier. Independent safety review programshalfbeconductedinaccordancewithwritten,approvedprocedures.
REVIEW
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Nuc\\ ear Assessment Department
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6.5.4.9 The C::p:::.t: Mu:1::: S:f:0 !:::!:: shall perform reviews of the followingt j
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
,j this review.
b.
proposed changes to procedures required by Specification 6.8,'and proposed modifications that constitute an.unreviewed-safety question i
as defined in 10 CFR 50.59 or a. change to the Technical Specifications, prior to implementation.
l BRUNSWICK - UNIT 1 6-11
. Amendment No. 138 i
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ADMINISTRATIVE CONTROLS REVIEW (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 Specifications, prior to implementation.
4 d.
Proposed changes to the Technical Specifications and Operating License.
Violations of applicable codes, regulations, orders, Technical e.
Specifications, license requirements, and internal procedures or instructions having nuclear safety significance.
4 f.
Significant operating abnorm 4.11tles or deviations from normal and expected performance of piant safety-related' structures,' systems, or eomponents.
g.
Reportable events.
h.
Reports and minutes of the'pNSC.
- Nuclear Assesstnerk De.onthmenh Anyothermatter(nvoljingsafeoperationofthehuclearpowerplant 1.
that the Manager - 0:,:::t: ";;!::: Sf;;y %:.ti;;. deems appropriate for consideration or which is referred to the Manager - S. p.;;;
".;!;;r R f;;, Ex:tir by,the on-site operating organization or other 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 investigations made and the recommendations resulting from these investigations to prevent or. reduce the probability of recurrence of the event.
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RECORDS h udeor Assessment Depachmed 6.5.4.11 Records od ^
p S:1 :: Sf.t> S::::: reviews, including' recommendatior.s and Io cern;;s;,;shall-be prepared and distributed as indicated n
belows Nuc\\ene AssessmenE Deportment-
- Copies of documented reviews shall be retained in the 4HGG-files.
a.
A b.
Recommendations and concerns shall be submitted to the General Manager - Brunswick Plant and Manager -_ Brunswick Nuclear Project :
l within 14 days of completion of the review.
Oe Nuc\\ ear Assessmenk Deparkmerth's c.
A summation of C::p ::: " ;i;;; R f:.y S ;;i:r'- recommendations and concernsshallbesubmittedtotheChairman/PresidentiExecutiveVice President - Power Supplyl Senior _Vice President - Nuclear Generation 1
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Vice President.- Nuclear Servicesi Hanager -' Brunswick Nuclear Project; Ceneral Manager - Brunswick Planti and others, appropriate, at least once every two_ months.
BRUNSWICK - UNIT 1 6-12
' Amendment No.,138
ADMINISTRATIVE CONTROLS i
NUCLEAR ASSESSMENT DEPARTMENT AUDIT PROGRAM 6.5.5 COPP^^'T OUALITY A00""A"Or AUP:T Pn00">."
FUNCTION Nuclecir Assessmenk De artenant The ;.; ' ;, A.....;; ^.. '.; ! ni; p;i; ';.' '.U } ;f ;h; C;. F..;; 0 ;11;j 6.5.$.1 l
';;rn:: 5;r'm shall function to perform audits of f acility activities specified in Specification 6.5.5.2.
AUDITS Nuc\\ ear M5essenent Department.
3-6.5.5.2 Audits of f acility activities shall be performed by the 4 mmh-These l
audits shall encompasst a.
The conformance of facility operation to provisions contained within the Technical Specifications and appilcable license conditions at least tnce 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 faellity equipment, structures, systems,.or methods'of operation.that, affect nuclear safety at least ones 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", 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 implementirs 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.
i.
The OFFSITE DOSE CALCULATIONAL 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.
i BRUNSWICK - UNIT 1 6-13 Amendment No. 138
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ADMINISTRATIVE CONTROLS I
AUDITS (Continued) k.
The performance of activities required by the Quality Assurance i
Program to meet the provisions of Regulatory Culde 1.21, Revision 1, June 1974, and Regulatory Culde 4.1, Revision 1, April 1975, at least once per 12 months.
4 1.
Any other area of facility operation considered appropriate by the l
Manager C.eiity !.;;,.r;.r.;; C:rci;;;
Q C;;; 1..
NucAear Assessmerk De Personnel perf orming the qu:1hy ec c _ partme.rk.
l 6.5.$.3 e m audits shall have-access to the plant operating records.
i RECORDS 6.5.5.4 Records of audits shall be prepared and retained.
NucAene Assenment "Deparkenent.
Audit reports e< compassed by 6.$.5.2 above shall be prepared, 6.5.$.$
approved by the Manager - Q-.!!:,.t; ;;.r.;; R:- !::: C:
!:, and forwarded to the Executive Vice President - Power Supplyl Senior Vice President - Nuclear Generationi Manager - Brunswick Nuclear Projecti "!:: ";;;!d:::
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C::vi::;l General Manager - Brunswick Planti and others, as appropriate, within 30 days after completion of the audit.
AUTHORITY NtAc3 ear Assessmank Departmenk-6.5.5.6 TheManager-fu: lit, S:::::::
hr"!::: S::t.:r d:: iS: ":::;;; -
Cer,::::: ; 11:y u;.;;r.:: shall be responsible for the following Scitor Aness, pent Depart:manh a.
The administering of the C::;;;;t: Qu..t; S: :_n:: Audit Program.
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b.
The approval of the individual (s) selected to conduct,- '.ity
-664 m enee audits.
PERSONNEL.
I 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.
l BRUNSWICK - UNIT 1 6-14 Amendment No. 138 l
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ADMINISTRATIVE CONTROLS 6.5.6 OUTSIDE ACENCY INSPECTION AND AUDIT PROGRAM 6.$.6.1 An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
6.5.6.2 An inspection and audit of the fire protection and loss prevention program shall be priormed by an outside qualified fire consultant at intervals no greater than 36 months.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken-for REPORTABLE EVENTSt-a.
The Commission shall be notified and a report submitted. pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Plant Nuclear Safety Committee - Brunswick Plant and shall be submitted to the Manager -
Cesp;ce;; !!.;;;;; C;f;;y R;;i;. and the Manager - Brunswick Nuclear j
Project.
L Nuclear Assessment Depczchment 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violatedt 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 l
possible and in all-cases within one hour. The Manager - Brunswick l
Nuclear Project and the Manager - C;r :::::y!!;;i;;; Rf;;, L.;L..
l shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
duclear Assessmenk DeparkmenE c.
A Safety Limit 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 Violation Report shall.be submitted to the Commissiop!!;;1;;; O f;;y R;;i;; within 14 days of the violation.
, the Manager - Brunswick Nuclear Project, and the Manager -
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Nuclece Asses 5 ment 7eparkment BRUNSWICK - UNIT 1 6-15 Amendment No. 138 s
ADMINISTRATIVE CONTROI.S RECORDS RETENTION (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.
m.
Records of analyses required by the radiological environmental monitoring program.
Records of (1) meetings of the PNSC, (2) meetings of the previous n.
off-site review organization, the Company Nuclear Safety Committee gs 3 thgin Ntreh,Cg'e[a),dy4,5(tependent reviews performed by the correrete Nvcky 4en, and (4) the independent reviews performed by ar-the Corporate Quality Assurance Audit Program, Quality Assurance Auditing Unit.
6.11 RADIATION PROTECTION PROCRAM 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 HICH RADIATION 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 followingt 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 af ter 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 4
radiation protection procedures for entry into high radiation areas.
BRUNSWICK - UNIT 1 6-25 Amendment No. 138
ENCIDSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 6 50 324 OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT NUCLEAR ASSESSMENT DEPARTMENT ORCANIZATION C hNCES TECHNICAL SPECIFICATION PAGES UNIT.2, f
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INDEX i
6 ADMINISTRATIVE CONTROLS SECTION PACE
.c 6.1 RESPONSIBILITY.............................................
6-1 6.2 ORCANIZATION i
6.2.1 0FFSITE AND ONSITE ORCANIZAT!0NS.......................
6-1 l
6.2.2 F MI L I T Y S T A F F..........................................
6-1
. E cQ M T _ h3 E H M EN I ( M) 6.2.3 sv..)
l Function...............................................
6 -
Responsibilities................................'.......
6-5 Authority..............................................
6-5 6.2.4 SHIFT TECHNICAL ADVIS0R................................
6-5 i
6.3 FACILITY STAFF QUALIFICATION...............................-
6-5~
6.4 TRAININC...................................................-
6-5.
6.5 REVIEW AND AUDIT-6.5.1 NUCLEAR SAFETY REVIEWERS...............................
6-6 6.5.2 SAFETY EVALUATIONS AND INDEPENDENT REVIEW CONTROL Safety Evaluations.....................................
6-6.
Procedures, Tests,'and Experiments.....................
6-7 Modifications..........................................
6-7 l
Operating License /Technicst -S pecifications.............
6-7 6.5.3 PLANT NUCLEAR SAFETY C0KHITTEE (PNSC)
Function...............................................
6-8 Composition....~........................................
6-8 A 1 t e r ra t e s.............................................
6-8 Heating Frequency......................................
. 8 Quorum.......................~..........................
6-8' Activities.............................................
6-9 Authority..............................................
6-10 Records................................................
6-10_
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.l BRUNSWICK - UNIT 2 XIV Amendment No. 170
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INCEX ADMINISTRATIVE CONTROLS SECTION PACE 6.5 REVIEW AND AUDIT (Continued)
ASS {bCAA-0ATCTY SECTION$sMENT DEPARNE4T* INDEPENDENT RE N
- "Ju Function......................................
6-10 Organization............................................
6-10 Reviev..................................................
6-11 Records.................................................
6-12 NUCLEAR ASSESSMENT DEPARTMENT 6.5.5
-e M POPJ,T ^L'AL!TY AGGMANGB AUDIT PROCRAM Function................................................
6-13 Audits..................................................
6-13 Records..............
6-14 Authority...............................................
6-14 Personnel...............................................
6-14 6.5.6 0UTSIDE ACENCY INSPECTION AND AUDIT PROGRAM.............
6-15 6.6 REPORTABLE EVENT ACTI0N....................................
6-15 6.7 SAFETY LIMIT VIOLATION.....................................
6-15 6.8 PROCEDURES AND PR0 CRAMS....................................
6-16 6.9 REPORTING REQUIREMENTS Routine Reports........................................
6-17 Startup Reports.........................................
6-17 Annual Reports..........................................
6-18 Personnel Exposure and Monitoring Report...............
6-18 Annual Radiological Environmental Operating Report......
6-19 Semiannual Radioactive Effluent Release Report..........
6-20 Honthly Operating Reports...............................
6-21 Special Reports.........................................
6-22 Core Operatin6 Limits Report............................
6-22 I
l l
BRUNSWICK 6 udIT 2 XV Amendment No. 170
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. ADMINISTRATIVE CONTROLS PROJECT A s ses.smca T C
%UCLEAR-3Ai2Ti (GWS) m) 6.2.3 OW917
~
FUNCTION Ph 6"f 6.2.3.1 The CW3 Un!i-shall function to examine facility operating characteristics, NRC issues, industry advisories, and other sources which may indicate areas for improving facility safety.-
RESPON9tBILITIES' PA Geof 6.2.3.2 The OMS-ttnh 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 Ph &<out 6.2.3.3 The ONS U.di shall make detailed reconunendations for revised I
procedures, equipment modifications, or other means of improving facility
[
saf ety to the Manager - C-5 wet e-Wacker-9ef;y %d =.
tN ew hsuss& : Defertovaf.
i 6.2.4 SHIlT TECHNICAL ADVISOR t
6.2.4.1 The Shift Technical Advisor shall serve'in an advisory capacity to the Shift Operating Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.3 FACILITY STAFF QUALI'ICATION 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Manager - Environmental & Radiation Control who shall meet or exceed the qualifications of Regulatory Culde 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or er,ineering discipline with specific training in plant design, and response and analysis of the plant during transients and accidents.
6.4 TRAININC 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 $5.
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.
i
- Not responsible for sign-off fun.,. n.
BRUNSWICK - UNIT 2 6-5'
' Amendment No.-170
ADM8NZSTRATIVE CONTROLS 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 determination, 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 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 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 shell 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 Specification. or constitutes an unreviewed safety question as defined in 10 CFR 50.59.
6.5.2.7 Following the nuclear safety review, 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 Specifications shall be approved by the General Manager - Brunswick Plant or his previously designated alternate.
OPERATING LICENSE / TECHNICAL SPECIFICATIONS l
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 bel l
a.
Reviewed by the Plant Nuclear Safety Committee in accordance with specification 6.5.3.8.
b.
Reviewed by the-Cerp:nt:Nuciece Assessme.nb Dep::rtment
" :hn Rf ty.
t!:= in accordance with l
Specification 6.5.4.9.
A BRUNSWICK - UNIT 2 6-7 Amendment No. 170
ADM?NfSTRATIVE CONTROLS ACTIV! TIES 6.5.3.8 The PNSC activities shall include the followings Review of all procedures required by Specification 6.8 and changes a.
thereto (and any other procedure 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,.
. prior tu implementatlon.
d.
Review of all proposed changes to the Technical Specifications or Operating License, prior to implementation.
Review of reports on violations of Technical Specifications including e.
reports covering evaluation and-recommendations to prevent ~ recurrence to the Manager - Brunswick Nuclear Project and to the Manager -
l C::;::::: "::1::: S:fety 5::t!:. Nuclear Assessment Veportment. -
f.
Performance of special reviews, investigations (or. analyses), and reports thereon as requested.by the Manager ---C::;:::te u :12:r Sdety u
S::ti::a Nuc\\cor Assessment Department.
g.
Review of all REPORTABLE EVENTS.
h.
Review of facility operations to detent potential nuclear safety
~
hazards.
1.
Annual review of the Security Plan.
j.
Annual review of the I'mergency Plan.
k.
Review of accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations ano disposition of the corrective action to prevent recurrence and the forwarding of thess' reports to the Manager -
l Brunswien Nuclear Project-and the Manager --C::p:::t: " :10 : S:fety S :t1;h-hjucleot At6essmenk. Deparkment.
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
l BRUNSWICK - UNIT 2 6-9
- Amsndment No.~170 r
_. - ~ _
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ADMINISTRAT!UE CONTROLS i
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 Ceneral Manager - Brunswick Plant to be the most conservative shall be followed.
RECORDS 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 provisions of these Technical Specifications. Copies shall be provided.to the Manager - Brunswick Nuclear Project and the Manager - 0;.r;;;;; "2:!07 Saf;t'/
-seethm, Nucleoc Asses.sment Department.
If!I'bLb_ b T.
O.,E T NDEPENDENT REVIEW PROGRAM 6.5.4 0
FUNCTION 3
.....1 6.$.4.1 The
...r.....-
Dep:::r::: shall function to provide independent review of significant plant changes, tests, and procedurest verify that REPORTABLE EVENTS are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such eventsi and detect trends that may not be apparent to a day-to-day observer.
ORCANIZATION 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 areast a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry l
d.
metallurgy e.
non-destructive testing f.
Instrumentation and control l
l g.
radiological safety h.
mechanical and electrical engineering 1.
administrative controls
.l BRUNSWICK - UNIT 2 6-10 Amendment No. 170 1
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ADMINISTRATIVE CONTROLS ORGANIZATION (Continued)
J.
seismic and environmental k.
quality assurance practices 1.
Other appropriate fields associated with the unique characteristics of the nuclear power plant.
Nuc.lcetr ASscuimed p@; met.
6.5.4.3 TheManager-greepecett-%ee4c: h...,
. ;t;= shall have an academic 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.
Nuclear Assessment T>eposetment N 6.5.4.5 An individual may possess competence in hare than one specialty If suf ficient expertise is not available within the % resi ; 4-i --
area.
R f;;, n ; O n, competent individuals from other Carolina s'ower & Light Company organizations or outside consultants shall be utilized in performing independent reviews and investigations.
6.5.4.6 At least three individuals, qualified as discussed in 6.5.4.4 above, j
shall review each item 6ubmitted 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.
Nucieor A3eessmerrk T>ep;;etment; 6.5.4.8 The O.r..
.. L;i;;. % %;, -
i n independent safety review programshalfbeconductedinaccordancewithwritten,approvedprocedures.
REVIEW
-l Nucleoc Assessment Departme.nt 6.5.4.9 The %. re. te L;i;;;~ L hty L:W :-shall perform reviews of the 3
followings 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 i
Specifications.
Implementation may proceed prior to completion of l
this review.
l l
b.
Proposed changes to procedures required by Specification 6.8, and l-proposed modifications that constitute an unreviewed safety question l
as defined in 10 CFR 50.59 or a change to the Technical Specifications, prior to impletcentation.
i BRUNSWICK - UNIT 2 6-11 Amendment No. 170
]
i ADMINISTRATIVE CONTROLS 1
REVIEW (Continued) c.
Proposed tests or experiments that involve an unreviewed safety queetion as defined in 10 CFR 50.59 or a change to the Technical Specifications, prior to implementation.
d.
Proposed changes to the Technical Specifications and Operating License.
e.
Violations of applicable codes, regulations, orders, Technical l
4 Specificaticos, license requirements, and internal procedures or.
instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and l
expected performance of plant safety-related structures, systems, or components.
g.
Reportable events.
l h.
Reports and minutes of the'PNSC.
l
- Nuclear Assessment " Department Anyothermatterhvofingsafeoperationofthenuclearpowerplant i.
that the Manager - -C r e:::;; '!u; h: Sf:ty S::h deems appropriate for consideratiog:or which is referred to the Manager - S.;;.;;;
S:h:: S hty S. t!:: by the on-site operating organization or other 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 investigations made and the recommendations i
resulting from these investigations to. prevent or reduce the probability of recurrence of the event.
RECORDS Nucicoc Assessment Dep:ar4.rnent 6.5.4.11 Records of S re::::: M :h:: S hty S t! n reviews, including 3
recommendations and concerns, shall be prepared and distributed as indicated below NucAcar Assessment Department a.
Copies of documented reviews shall be retained in the 4NGG. files.
^
l b.
Recommendations and concerns shall be submitted to the General Manager - Brunswick Plant and Manager - Brunswick Nuclear Project, l
within 14 days of completion of the review.
A summation of ": p:t Assessmenh Department's the Nucien l
.;; S: h ; R h.y S::i::'
recommendations and i
c.
concerns shall$e submitted to the Chairman /Presidenti Executive Vice President - Power Supplyl Senior Vice President - Nuclear Generation).
Vice President - Nuclear Servicesi Manager - Brunswick Nuclear.
Project Central Manager - Brunswick Planti and others, appropriate, at least once every two months.
BRUNSWICK - UNIT 2 6-12 Amendment No. 17b
i i
I ADMINISTRATIVE CONTROLS 6.5.5 Ph^ $E
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FUNCTION b... )?.F, i.._ _9.._iII?"M egygg,u.g
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6.5.5.1 The
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"::::- :: D:petr shall function to perform audita of facility activities specified in Speci,1 cation 6.5.5.2.
AUDITS Nuclear Assc%menk bepartment. 3 6.5.5.2 Audits of facility activities shall be performed by the QAAW-These l
audits shall encompasst a.
The conformance of facility operation to provisions conta!ned within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The training and qualifications of the entire facility staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in l
c.
facility ertuipment, structures, systems, or methods of operation that affect nuclear sa & v at least once per 6 months.
d.
The verification of compliance and implementatier. 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 pu 12 months.
h.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
i.
The 0FF3ITE DOSE CALCULATIONAL HANUAL and implementing procedures at least once per 24 months.
)
I j.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
l l
l l
l BRUNSWICK - UNIT 2 6-13 Amendment No. 170 l
1 I
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=
I ADMINISTRATIVE ' CONTROLS 1
AUDITS (Continued) k.
The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Culde 1.21 Revision 1 June 1974, and Regulatory Cuide 4.1, Revision 1, April 1975, at least' once per 12 months.
1.
Any other area of facility operation considered appropriate by the
~
Manager - Q :1!:) ^::r := S --!::: N:t!:r U Nuc. lear Assessment: Department.
6.5.5.3 Personnel performing the 79 !iy 2:ere r audits shall have access to the plant operating records.
RECORDS 6.5.5.4 Records of audits shall be prepared and retained.
( Nuclear Assessment Department 6.5.5.5 Audit reports er approved by the Manager gompassed by 6.5.5.2 above shall be prepared, Q.:lity *,:;;;;;;; hr^!=: h: tion, and forwarded to the Executive Vice President - Power Supply Senior Vice President - Nuclear Generationt Manager - Brunswick Nuclear Project; "!:: ":::!d::t
";;1: =
- h. k:e;-General Manager - Brunswick Planti and others, as appropriate, within 30 days after completion of the audit.
AUTHORITY Nuclear Assessment Department 6.5.5.6 The Manager
^ =lity ^.= ; = n h v. n : S::!= =d:: th:_ "=:;i::
5 pn::: Q::1!:y ^.n=::= shall be responsible for the followingt Nuclear AssessmeJ*:. Department. it Program.
The administering of the 4+epr :: Qu:1. y ^.:. x;; n Aud a.
b.
The approval of the individual (s)-selected to conduct ;=!!ty
<>eeweeeee-aud i t s.
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 conenensurate 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.
l 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.
BRUNSWICK - UNIT 2 6-14
' Amendment No. 170 1
i
ADMINISTRATIVE CONTROLS
.i 6.5.6 OUTSIDE ACENCY INSPECTION AND AUDIT PROGRAM 6.5.6.1 An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utillaing either qualified offsite licensee personnel or an outside fire protection firm.
s 6.5.6.2 An inspection and audit of the fire protection and loss prevention l
program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months.
6.6 REPORTABLE EVENT ACTION l
6.6.1 The following actions shall be taken for REPORTABLE EVENTSt The Commission shall be notified and a report submitted pursuant to a.
the requirements of Section 50.73 to 10 CFR-Part 50, and-b.
Each REPORTABLE EvC" ahall be reviewed by the Plant Nuclear Safety Committee - Bruhrvick Plant and shall be' submitted to the Manager -
C:c;; ::: !!;:1::: S:f t-; S::t!^ and the Manager - Brunswick Nuclear Project.
t g
Nuclear Assessment Department.
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.
s b.
The NRC Operations Center shall be notified by telephone as econ an possible and in all cases within one hour.
Nuclear Project and the Manager - 0 :p:::::qThe Manager - Brunsviev, l
!!;:!::: :f::y ;;;;i n
[
shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Nuclear Assessment Deparkmtot A Safety Limit Violation Report'shall be prepared. The report r.htiit c.
be reviewed by the General Manager - Brunswick Plant. This rep 9tt l
shall describe (1) appilcable circumstances preceding the violet-190 (2) effects of the violation upon facility cornponents, systems, nr structures, and (3) corrective action taken to prevent recurren a d.
The Safety 1,!mit Violation Report shall be -submitted to the Commissieg!!;;1:::, the Manager - Brunswick Nuclear' Project, and the Hamor -l' Cc,sps,r ::
S:f:t-/ S::t!^~ within 14 days of the violatints l
Nuclear ASSessrnenh Deporbmerk BRUNSWICK - UNIT 2 6-15 Amendment No. U S a
~ - -. -~
e a
a s
1 ADMINISTRATIVE CONTROLS-ij RECORDS RETENTION (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 tho' 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.
1 m.-
-Records of-analyses required by the radiological environmantal i
monitoring program.
i Records of (1) meetings of the PNSC, (2) meetin6s of the previous.
~l n..
off-site review organization, the Company Nuclear Safety Committee N.Mid3djh,p,,ig_ dependent reviews performed by the Orps.te Nvder 8
m y... ac., and (4) the independent reviews performed by a m...
the Corporate Quality-Assurance Audit Program, Quality Assurance l
Auditing Unit.
3 6.I1 RADIATION PROTECTION PROCRAM~
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 HICH RADIATION AREA 6.12.1 In lieu of the " Control Device" or "alarru signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high.radlAtton area in which the intensity of radiation is 1000 meem/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-O provided with or accompanied by one or more of the'followingt'
- (
A radiation monitoring device which conticuously indicates: the a.
radiation dose rate in the area.'
l b.
A radiation monitoring device _which continuoosty Integrates the g
radiation dose rate in'the_areaLand' 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 atet have been established and personnel havs been_made knowledgeable of them.
- Health Physics personnel or-personnel escorted by Health Physics personnel i
shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they coinply with approved radiation protection procedures for' entry into high radiation' areas.
l BRUNSWICK - UNIT 2-6-25'
-Amendment'Ho. 170 i
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