ML20086P384
| ML20086P384 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/18/1991 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20086P378 | List: |
| References | |
| NUDOCS 9112270009 | |
| Download: ML20086P384 (57) | |
Text
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i 1 ATTACHMENT 1 1 1 PROPOSED CHANGES i ? [. 91'12270009 911218
. PDR ADOCK 05000413 P PDR
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall unit opera-tion and shall delegate in writing the succession to this responsibility during ais absence. 6.1. 2 The Shift Supervisor (or ouring his absence from the control room, a designated individual) shall be responsible for the control room command function. A management directive to this effect, signed by the Vice Presiden of Nxlest IrcdweMen, shall be reissued to all Nuclear Pnductic Ocp;rtment-s.t+ Men--personnel on in annual basis. . 6.2 ORGANIZATION
# *' #~ l 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and Lyy curporal.e management, respectively. The onsite and offsite organizations J.p snali include the positions for activities affecting the safety of the nuclear power plant.
o h g a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through
.1) 3cr 4 intermediate lavels to and including (11 operating organization f 3# '
positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional Fy uz y h.f descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms E- of documentation. These requirements shall be documented in the 6 FSAR.
$ggLp m b. The Station Manager shall be responsible for overall unit safe Od operation and shall have control over those onsite activities hd necessary for safe operatig an maigtenancegfJheplant, The Vice President ofkdcM(cEctfchs511 haN corporate-gQ3 c. responsibility for overall plant nuclear safety and shall take any 9A.} Zu b measures needed to ensure acceptable performance of the staff in M% o> E og operating, maintaining, and providing technical 5 oport to the plant to ensure nuclear safety. - .
*,& The incividuals who train the operating staff and those who carry fh)4bh out health Fsics and quality assurance functions may report to the appropriate dsite manager; however, they shall have sufficient y organizationa' freedom to ensure their independence from operating pressures.
6.2.2 UNIT 5TAFF b^ 'Y o d F O
- a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1;
- b. At least one licensed Operator for each unit shall be in the control room when fuel is in the reactor. In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; CATAWBA - UNITS 1 & 2 6-1 Amendment No. 56 (Unit 1)
Amendment No. 49 (Unit 2)
n= [e ADMINISTRATIVE CONTROL g ^ggg LUNITSTAFF(Continued) g
- c. A WeeMh it: TechniciaOsha11be.onsitewhenfuelisineither reactor; di - All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited
-to Fuel Handling who has no other concurrent responsibilities ddring this operation;-and
- e. . (Deleted) ggy N 'II "
- f. LAdministrative procedures all be d loped and implemented to limit the working hours o staf who perform safety-related functions (e.g. , licensed Senior. Operators, licensed Operators, C L Hth :,hv;ic ste. ux!!!:rv :::r:tTes. and key maintenance personnel).
N W laA.id ht e e.tio a tech n ic_i a n.s l . Adequate shift coverage shall be maintained without routine heavy use of: overtime l The objeci.ive shall be to have operating personnel
-work a normal 12-hour day with alternating.48-hour and 36-hour work weeks while the unit -is' operating. However, in'the event that i unforeseen problems require'substa7tial amounts of overtime-to be used,;or during extended periods of shutdown ~for refueling, major maintenance,-or major plant modification, on a temporary basis the following guidelines shall be followed:
- 1) ,An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time.
- 2) An individual-should not be permitted to work more than 16 hours in any 24-hour.' period, nor more than 24 hours in any 48-hour period,Enor more than hours in any 7-day- period, all excluding shift-turnover time.
3): A break of at_least S hours should be allowed between work periods, including shift turnover time.
-4) $xceptduring.extendedshutdownperiods,theuseofovertime should be considered on an. individual basis and not'for the entire staff on a shift.
.Any deviation from the above guidelines shall be authorized by the Station Manager or his designee, or higher levels of management, in accordance uith established procedures and with documentation of the basis for' granting the deviation. Controls shall be' included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that excessive hours have nottbeen. assigned. . Routine deviation from the above guidelines is not authorized.
"The' i lth "hy;ics Technician may be 12:s th;n the P n H r requircrent: f0r ;
i peri d of tim; nn-t; cxeced 2 heur;, in Order te eccc-adate unexpected eb; nce, pr4vided 4-~H=ta ar-t inn i c + een_t +4 the required pc:ition;. CATAWB?,.- UNITS 1 & 2 6-2 Amendment No. 91 (Unit 1) Amendment No. 85 (Unit 2)
~ ~ _ _ _ _ _ _ =
ADMINISTRATIVE CONTR01. UNIT STAFF (Conting i I '
- g. Thedupe t n iconse. The 0--- ineer, Shift Reector ra r Supervisor and As stant Shif t Supkrvide;&'7)Oerationss sha l h id an SR0 l
-license. The Reactor Operator shal < hold a Reactor Operator License, i Opero b wr> MN3d l
t l Y T l t t 1 i CATAWBA - UNITS 1 & 2- 6 2a Amendmeht No. 56 (Unit 1) . Amendment- No. 49. (Unit 2) - . iwwp. e9 w- ,cw- ,e .s v o4 _,,- ~ ~f-p,r,y.r- r,,y-4 .,,y . , , , - . _ .y y- y . , ,rg..~,-gy,,g m., 3 y- w,-e,,... ,-,,m-. .,, ,me.' wa-, n.. ume
i a , , TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Both Units in One Unit in Mode 1, 2, 3 or 4 Both Units in Mode 5 or 6 and Mode 1, 2, 3 or 4 or Defueled One Unit in Mode 5 or 6 Defueled s SS 1 1 1 SRO 1 None## 1 R0 3# 2# 3# NEO ' 3# 3# 3# HA 5 M 1 None 1 SS - Shif t Supervisor with a Senior Operator license SR0 - Individual with a Senior Operator license RO - -Individual with an Operator license NEO. - Nuclear Equipment Operato p L5E}+ 4TA--- SMft Tech..icel Aeinof f5 hi H M ono 3e r The Shift Crew Composition may be one less than the minimum requirements of Table _6.2-1 for_a period ef time not to exceed 2 hours in order to accommodate unexpected absence of on-dt.ty shif t crew members provided immediate action is: taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman _being late or absent. During any absence of the Shift Supervisor from the control room while the shif t unit is in MODE 1,.2, 3, or 4, an individual _(other than the Sht T P N M a m @ ~ r-
-Advisor") with a valid Senior Operator license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator license or Operator license shall be designated to assume the .;ontrol room command function.
ShiH thnagei~ ) Shift Supervi r and the SRO
*0n_occasionwhenthereisaneedforboththyhallbeallowdtoassumethe to be absent from the control room. the 4TA s control room command function and serve as the SRO in thq/ control room provided that: (1) the Shift Supervisor is available t / return to the control room within 10 minutes, (2) the assumption of 5 0 duties by the M
.be limited to periods not in excess of 15 minutes dura ion and a total time:
.not to exceed 11 hour during any shift, and (3) the fri has a Senior Operator l license on the unit,
#At least one of the required individuals mu>t be assigned to the designated position for each unit.
L i ##At'least one licensed Senior _ Operator or licensed Senior Operator Limited to Fuel Handling must be present during CORE ALTERATIONS on either unit, who has no other concurrent responsibilities. CATAWBA' = UNITS 1 & 2 6-5 Amendment No. 37 Unit 1) Amendment No. 29 Unit 2) l
, l
~ ADMINISTRATIVE CONTROLS !
6.2.3 CATAW8A SAFETY REVIEW GROUP FUNCTION ! SRG) thall function to provide the 6.2.3.1TheCatawbaSafetyReviewGroup((ienceforpotentialopportunities review of plant design and operating exper ! improve plant safety; evaluation of plant operations and maintenance 1 activities;'and, to advise management on the overall quality and safety of , plant operations. The I.SRG shall make recommendations for revised procedures, equipment modificetions), or other means of improving plant safety to , appropriate station / corporate management. COMPOSJTION 6.2.3.2 The $RG shall be composed of at least five, dedicated, full-time {
) NrW hc ! bi, c e$a s (1) -A' bachelor's degree in engineering or related scienc,! and at least 2 years professional 1svel experience in his/her ficid, at least 1 year..
of which experience shall-be in the nuclear field; or, i (2) At least 5 years of nucler.r experience and hold or have held a Senior Reactor Operator license; or ( (3) At least 8 years of professional level experience in his/her field, at ; least 5 years of which experience shall be in the nuclear field. A minimum of.i (of-thesepersonnelshallhavethequalificationsspecifiedin l (1) above. J. RESPONSIBIt.ITQS 6.2.3.3 TheKSRGi s hall-be responsible for:
- a. . Review of s' elected plant operating characteristics and other appropriate- sources of plant design and operating experience l
information for awareness and incorporation into the performance of other duties.- ^
- b. Review of the effectiveness of correctivo actions taken as a result of ?he evaluation of selected plant operating characteristics and other appropriate sources of plant design and operating experience information,
- c. Review of selected programs, procedures. and plant activities, including maintenance, modification, operational problems, and.
operational analysis. 1 s r CATAWBA - UNITS 1 & 2 6-6 Amendment No77 (Unit 1) Amendment No71 (Unit 2)
- __ _ . . _ _ _ .._.._ _ ~ _ , . _ . - . _ . _ . _ . _ _ .
i
- f ADMINISTRATIVE CONTROLS _
RESPONSIBILITIES (continued)
- d. Surv0lllance of selected plant operations and maintenance activities F to provide independent verification
- that they are performed correctly and that human errors are reduced to as low as practicable,
- e. Investigation of selected unusual events and other occurrences as assigned by Station Management or the Manager of K ar Safety Assurance. ,
AUTHORITY _ 6.2.3.4 TheNSRGshallreporttoandadviset..aManagerofM :r Safety Assurance, on 1. hose areas of responsibility specified in Section\:6.2.3. RECORDS 6.2.3.5 Records of activities performed by the' SPG shall be prepared and ! maintained for t , life of the station. Summary .eports of activities perfqrmpd by the RG shall be forwarded each calendar month to the Manager of "oger Safat ssurance. 6.2.4 SHIFT TEC*! CAL--ABVMOR f(lo.nacje r~ 6.2.4.1 The $hift Tec H ed %icerghallserveinanadvisorycapacityto , the Shift Supervisor. r ; g, hose. Funcb o ws m c\v de. % o sc. * " l A T#C "' "" ~ 6.3 UNIT STAFF _ QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for. comparable positions, except for the Radiation - Protection Manager, who shall meet or exceed the qualifications of Regulatory ' Guide-1.8, September 1975. -The licensed Operators and Senior Operators shall-also meet or exceed the minimum qualifications of the supplemsntal require-ments;specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.** , 6,,,J, TRAINING 6.4.1 A retraining and replacement training program for the unit itaff shall be maintained under the direction of the "m; r, StatietT rainingr5mh:: and I ' 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 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant
. industry operational experience. l t
*Not responsible for sign-off function.
**Except that the experience and other considerations described in Duke Power Company's letters dated August 28, 1985, and July 8, 1986, are acceptaole for the six and two applicants for SR0 licenses identified therein, respectively.
CATAWBA - UNITS 1 & 2 6-6a Amendment No. 80 (Unit 1) Amendment No. 74 (Unit 2)
.f
.- 4 . < . - -
ADMINISTRATIVE CONTROLS _< ~ 6.5 RWIEW AND AUDIT
- 6. 5; '4 f TECHNICALREVIEWAND_CONTROLACTJVITIES 6.5.1.1 Each procedure and program required by Specification 6.8 and other ;
procedures which affect nuclear safety, and changes thereto, shall be prepared '
-by a qualified individual / organization. Each such ,v scedure, and changes thereto, shall be reviewed by an individual / group other than the individual /
group which prepared the procedure, or changes thereto, but who may be from ' the same organization as the individual / group which prepared the procedure, or changes thereto. ' 6.5.1.2 Proposed changes to the Appendix A Technical Specifications shall b_e prepared by a qualified individual / organization. The preparation of each ; proposed Technical Specification change shall be reviewed by an individual / ' group other than the individual / group which prepared the proposed change, but who may be from the sar,e organization ar, the individval/ group which prepared the proposed change. Proposed changes to the S be approved by the Station Managerg- hili ~~cll e gneG.bninLfpecifications e-i shall ' ' 6.5.1.3 Proposed modifications to-unit nuclear safety-related structures, t systems, and components shall be designed by a qualified individual / organization. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be fron the same
- organization as the individual / group witch designed the modification. Proposed
' ke paced mod 444eetions-to-nuclear safety telste.1 structures r-4ysrtemfrr-end-components gg- s hall k --epp med-pe4 o r-to-itspleme n t%4on-by-the-$ta tion-fiansperi-cr-try-the g 'O p e r4t4 ng-Steerinte nden tr4 he -Techn$ He ni ce s-E vje Moteno tntrthe-Hein t enance 3y Superintend t, :n the-Superi-ntenden, ef 4nteeeated4chedutLigr-as-prev 4euMy-- des 4;neted t, tbStation-ttanager, p. Q g,;gg- - 6.5.1.4 !adividuals responsible for reviews performed in ac dance .withyd Specifications 6.5.1.1,6.5.1.2,and6.5.1.3shallbemembgrsoftheftet!en supervisory staff, previously designated by the Srtat4en Me...ger to perform such reviews. Review of environmental radiological ar,alysis procedures shall be performed by theAepeeate 5,5tein M i G Phj5icist or his designee. Each such review shall include a determination of whether or not additional, cross-disciplinary, r iew is necessary, if deemed necessary, such review shall be performed by e appronriate designated stat W personnel,
- 6. 5.1. 5 P L es+d-tett-and-exper %ent; die A est4tatic.~ nudear s a fet-y .
and_u s ' derested n ' t he F SA D or Technic 21-6 pee 4 Heat 4 ens-sheli be rwiewed- ,%Mb by-th at4cn-Mona4+r-er- by the Operat4cg Sweriidender L,--the Tec 'i:al IArA *Sarait s - Superintensn , + ha Main!= nance 5t;er int +ndent-ee-the-Superntudent- _E cLl r+ted-Schedu14- 9r-45-p+ +v40usly-designated by he- Station-ftantier,
% w sc & enunc & w as. .
l r CATAWB+ 1T5 1 L 2 6-7 Anendmert No.?? (Unit 1)
. - .- . . . . -_ - _. . _ _ _ . - _ - - _ = - . .- . . - -
INSERT A Proposed modifications to nuclear safety-related structures, systems, and components shall be approved prior to implementation by the Station Manager; or for the Station Manager by the Mechanical Superintendent, the Operations Superintendent, the I and E Superintendent, or the Work Control Superintendent, as previously
- designated by the Station Manager.
INSERT B , Proposed tests and experiments which af fect station nuclear safety. and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or for the Station Manager by the Mechanical Superintendent, the Operationn Superintendent, the. I and E Superintendent, or the Work Control Superintendent, as previously-designated by the Station Manager. b 4 m P t
,- - ~ ,, .- - - . . . . . - . . , . . - , . , . - - . .,,.,,n . . , . , .
. ADMINISTRATIVE CONTROLS TECHNICAL REVIEV AND CONTROL ACTIVITIES (Continue @ P'j" "'
6.5.1.6 All REPORTABLE EVENTS and alpvi n Technical Specifications shall be investigated and a repor repared_j wh ch evaluates the occurrence and which provides recommendatior o prevp t' recurrence. Such reports shall be approved by the Stat!cr "ent',er anAdransmitted to the Vice President, Nwc4eee Pre k:tioni and to the Nuclea (fety Review Board. p'N W e_}
- 6. 5.1. 7 The Statier "an:ger shall assure the pr'rformance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the V~.ce Presjdent. W e4 ear a-;i.; tion.
\S W ea I)de3 e d 6. 5.1. 8 TM statica secerd ty pre; rem, =d imp!:- nting preceWm : hem-be.
regiewed at-least ence per 12 : nths. Reec.x,.;n e d thenges she!!-44-Approved by the Sup:rint;nd;nt-cf St: tion Service; :nd tr:n:ritted te the-V4ee-President, Nuc.len e PrMortine , end to the ue !4ar Safety h vir.; Seard. ge@d [ 6.5.\ 1.9 TM statier r: ;ency plan, rd invi=;nttag precedures,-shall be reviews 4 :t 1:::t On:: per 12 ::nths. h;ex.;.r,ded ch;nge :ha'l be appr-eved by the -Statica ",;n;;;r :nd=teesmittM te- th: V4ce Pre;4tientrNueleer Dreduct4an, sad +e the ue :10:r %fety hvie. Board. (Ty\o.no.ge 5 6.5.1.10 The m static 5 ,enwer- "t a F e shall +q A55vre ce__1 assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwa.rding of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Vice Pres 4 dent, "rleer Pr;? -" n and to. the Nuclear Safety Review Board, g. g 6.5.1.11 Th.Qt:t!= "r:;:r shall assure the ' performance of a review by a qualifed int idual/ organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CAJ.CULATION MAMUAL. and Radwaste Treatment Systems. 1 mananer, Sake % h s.v ranc.c ) 6.5.1.12 Th( . - - - . . . shall 4ssure the performance of a review by a qualified inoividual/ organization of the Fire Protection Program and implementing procedures and the submittal of recommended chanjes to the Nuclear' Safety Review Boardypnd thp ag e r, Human ke.lo u re d 5._1 6.5.1.13 Reports documenting each of tpe activities performed under Specifications 6.5.1.1through6.5.1.J1shallbemaintained. Copies shall be provided to the Vice Pr uident, Nuc1 ar Production, and the Nuclear Safety Review Board. K l3TE l 6.5.2 NUCLEAR SAFETY LEVIEW BOARD (NSRB) _ FUNCTION 6.5.2.1 The NSRB shal' function to provide indepGudent leview and audit of designa:ed activities 'n the areas of:
- a. Nuclear powe plant c;erations,
- b. Nuclear engireering,
- c. Chemistry anc radiochemistry, CATAWBA - UNITS 1 & 2 6-8 Amendment No. 81 (Urit 1)
Amendment No. 75 (UMt 2)
ADMINISTRATIVC CONTROLS FUNCTION (Continued)
- d. Metallurgy, -
- e. Instrumentation and, control,
- f. Radiological safety,
- g. Mechanical and electrical engineering, and
- h. Acministrative control and quality assurance practices.
The NSRB shall report to and advise the V4ceJees44snty-#wc4eee4rvduv.,ioff, on those areas of responsibility specified in Specifications 6.5.2.8 and 6.5.'.9. _ORGAtIZATION EXccubve. Y ca. 3 c6.dtni h m ec be ne M i60 6.5.2.2 The Director, m rs, and alterrite members of the NSRB shall be appointed in writing by the 4+Jre+44ent, NucleaeWeduc44e, and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas given in Specification 6.5.2.1. m O o Nmore than two alternates shall participate as voting members in NSRB C-" ' activities at any one time.
\ Genenkio n \
6.5.2.3 TheHSRBshallbecomposedofatleastfivemembersfincludingthe Director. Members of the NSRB may be from the Nuclear h ed w den Department, from other departments within the Company, or from external to the Company. A maximum of one member of the NSRB may be from the Catawba Nuclear RagnQ- site } staff. 6.5.2.4 Consultants shall be utilized as determined by the NSRB Director to provide expert advice to the NSRB. 6.5.2.5 Staff assistance may be provided to the NSRB in order to promote the proper, timely, and expeditious performance of its functions. 6.5.2.6 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at, leer.t once per 6 months thereafter. 6.5.2.7 The quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these Technical Specifications shall consist of the Director, or his designated alternate, and at least four other MSRB members including alternates. No more than a minority of the quorum shall have line responsibility for operation of Catawba Nuclear Station. . van for
& s p c ia l cu e q tcen d , hb Age ini men t w &# an ,
- v. ca. d e m i c. in enc ce f h y iC.cd 5ctc nc t-c..drN d e, S e c eI , e d w ghi nnc.c0h0o 4 c) f e c i g n t t3 c u s Q P -
rnu g e ,_ rj mi s ( nce. s .e. cnc ee n e o .- w s <n dpu i e , c o , em v . 5 . .t .1 CATAWBA - UNITS 1 & 2 6-9
ADMINfSTRATIVE CONTROLS REVIEW 6.5.2.8 The NSRB shall be responsible for the review of:
- a. The safety evaluation for: (1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not consti-tute an unreviewed safety question. ,
- b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR;
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR;
- d. Proposed changes in Technical Specifications or this Operating License;
- e. Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance;
- f. Significant operating abnomalities or deviations from normal and expected performance of unit equipment that affect nuclear safety;
- g. All REPORTABLE EVENTS;
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety;
( N e.e W e.a % W l
- i. QualityN s vance Department audits relating to station operations and actions aken in response to these audits; and
- j. Reports of activities performed under tpe provisions of Specifications 6.5.1.1through6.5.1.J.I.
1;L. AUDITS 6.5.2.9 Audits of nLt activities shall be performed under the cognizance of tne NSRB. These audits shall encompass:
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at--4 east once-per-12-months; g
- b. The performance, training, and qualifications of the entire e t staf f at-4 east--once4eMMnusr; CATAWBA - UNITS 1 & 2 6-10
. r ADMINISTRATIVE CONTROLS t
AUDITS (Continued) c . -- The results of actions taken to correct deficiencies occurring in i unit equipment, structures, systems, or method of operation that affect nuclear safety att:Lg4-per 0 sivnih5;
- d. The perforinance of activities required by the Operational Quality Assurance at.1 e s t :. ( W ., 24 a.er.th:;roggamtomeet_thecriteriaofAppendix ,
- e. The ence per
.L.Jmergency Plan and implementing procedures at 1 pi6ns; '
'f. The-Security n_ iz_ a. . . ,. .
Plan and implementing procedures e
\u et l[\ < nc. per ,
- g. The Facility Fire Protection programmatic conjrols including the implementingprocedures at-4+ast encQW;ntu by qualified IP=-en g p:reerne!;
- h. Thefireprotectionequipmentandprogramimplementationahtt once$;(12a.enthsutilizingeitheraqualifiedoffsiteItcensee fire protection engineer or an outside independent fire protection consultant. An outside ind .,andent fire protection consultant shall be used at least every third year;
- i. TheRadio' log:ical'EnvponmentalMonitoringProgramandtheresults thereof :t . est g po 12 c.efittis; j_
The OFFSIT(DJ5E, CALCULATION MANUAL and implementing procedures 4t-leet : .;em, muen.ns;
- k. The PROCESS CONTROL PROGRAM and implemc.9 ng procedures,,for gqc3ssing and packaging of radioactive wastes at-4+ cace per
. 7.. 9 u3,
- 1. The performance'of activities required by the Quality 4 Asjurance Progra for f nt and environmental monitoring :t g t ence I^ A sit e.1 m.- Any other area of M4. operation considered appropriate by the NSRB' or the Vic: Presid nt. Nusleer P roduditm. n l E f ee.vW c. W cc W e M 4 t % Fa # Oca # '8 9 6.5.2.10 Records of NSRB' activities shall be; prepared, approved, and distributed as indicated below: g p .
g .
)
? a. Minutes _of each SRB meeting shall be prepared, approved, and forwarded to th W ee "r;;ie ui., Nuwiser Pre d tiem and to the
-Executive Vice President,mPewer & c & within_ 14 days l following each meeting; Q p o w c,- G en e_= o.h e y (
CATAWBA - UNITS 1 & 2 6-11 E . . _ _ _ - . - - . . . _ _ _ ._ . _ _. i .'
ADMINISTRATIVE CONTROLS RECORDS (Continued) 6e.n i o e-
- b. Reports of reviews encompassed by Specificat on 6.5.2.8 above, shall be prepared, approved, and forwarded to the vice President, Nuclear L(;.eneraHo.J}tPreictka, and to the Executive Vice President, Power Geeup-JGenemhoo 1 l within 14 days following completion of the review; and U r15cn .'o r-1 1 G.c nent + i e w I
- c. Audit reports enqompassed by Specificatio 5.5.2.9 above, shall be forwarded to theWice President, Nuclear P :nctica, and to the Execu-tive Vice President, Power Gp up and to the management positions l responsible for the areas a0Bited within 30 days after completion of the audit by the auditing organization.
Y c.,e n cea Mo tj 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50 and b.s E EVENT shall be reviewed by the Station Manager; ordy Fo r t W Each REPORTAB(Superintendent;'(2) Technical kr?ces- Superintendent;\
1)Operat% 6b*iod ' bec6tcalG(3) Mmt=: 3 uperintendent; S or (4)J uperinte ent of hi g rated (na er r hesi %g, as previously designated by the Static Manager, and_the y e,. results of this review shall be submit ;ed to the N B and the - M i+cbVice President.Neciee, Fi vuuniun, g g gj wer k. Co^+vo ll 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: .
- a. The NRC Operations Center shall be notified b elephone as soon as possible and in all cases within 1 hour. The i f a tien U
and the NSRB shall be notified within ict 24 President hours. =N"O cac
\cperartc s \
- b. A Safety Limit Violationgeport shall be prepared. The report shall be reviewed-by the Oper...ng-Superintendent and Station Manager.
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;- 5., g
- c. The Safety Limit Violation Re rt shall be submitted to the '
Commission, the NSRB and the'Vice President 4cing vuuuiorr within 14 days of.the violation; and
- d. Critical operation of the unit shall not be resumed until authorized by the Commission.
CATAWBA - UNITS 1 & 2 6-12 Amendment No, 80 (Unit 1) Amendment No. 74 (Unit 2)
i I 4 ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and n.aintained covering the activities referenced belows
- a. The n ' cable procedures recommended in Appendix A of Regulatory Guidt i 33, Revision 2, February 19781
- b. The emergency operating procedures required to implement the require-ments of NUREG-0737 and Supplement No. I to NUREG-0737 as stated in l Generic Letter No. 82-33
~b e, (,e fcci FQc. Secttrity P1OrAmptementationW ,
\
tcicA ed Cs:crgncy alen 4 ple mntetionr-
- e. PROCESS CONTROL PROGRAM implementation; ;
- f. OFFSITE DOSE CALCULATION MANUAL implementation;
- g. Quality Assurance Program implementation for efflue.t and environmental monitoring;
- h. Fire Protection Program implementations ke- . Yc c We '* n i.
# -- 35 bI G'---~
6.8.2 Commitments contained in FSAR Chapter) hanges thereto, s Each procedure of Specification 6.8. I1 And c reviewed and approved by the S4+t4cn ":n:g.vor-bye--{1)-Operating-Superin-tendentr{tt Tech'nical-Services-SuMHatendentr(3FMaintenance Superintendent, oe-f4M v pe r inten44n t-of-letegret ed 4ehedttlingi-es -prev 40vs ly-de sign ated-by---
.the-Stat 4on-M:n:; r; prior to implementation and shall be review 2d periodically as set forth in administrative procedures. ForIAmel4ed Sci:n:q,'arMB procedures which implement offsite environmental, technical and laboratory ,
activities, the above review and approval may be performed by the/anager,
- PNdscticr. Environmental- Services or-4e649neted Technfeel-System- :;:- ia th ProductW 5"m&Deper4mentrin-14etbef-the-individttels-specified ebever 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro-videds gesqneeq
- a. The intent of the original proceduri is not altered
- b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and ge, gi'~p&jen-p cm.
- c. .The change is documented, reviewed, and approved by theT64:t hn' M 5 O P '
Manager; or byt--t14-Operat4ng-Sup:rintendentrQ}-Technical-Services Supacintendenty--f3FMaintenance-Stiperintmdent, or (4) Supef1MTMdent af__integr-ated-Schedulingr-et previourtruestynattd-trrtte%tierr
- Mange ; within 14 days of implementation.
- 6.8.4 The following programs shall be established, implemented, and maintained:
- a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the containment spray, Safety Injection, chemical
% b end-epproval.my be perforW by the supgghM;tg%=gfEg%RSO'.
Seev+een o CATAURA - UNITS 1 & 2 6-13 Amendment No. 92 Unit 1 Amendment No. 86 Unit 2 -
.4 .
I . i i l' NO CHANGES ON PAGES-6-14 ? through 6-20 i e a
+ - r,*-+ ,'---,, - - . v,*w ,,-,-,..,,-+-,-v-.,,,,e-. y - ~ --,.. - , ,, www'--,s - w,--.- , --. . y c-- .,
L - l ADMINISTRATIVE CONTROLS l i RECORD RETENTION (Continued) I
- h. Records of inservice inspections performed pursuant to these Technical Specifications;
- i. Records of reviews performed for changes made to proccdures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;
- j. Records of meetings of the NSRB and reports required by Specification 6.5.1.10;
- k. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life coamences and associated insta11atiot, and maintenance records;
- 1. Records of secondary water sampilng and water quality; and
- m. Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at spucified times and QA records showing that these procedures were followed.
6.10.3 Records of quality assurance activities required by the Operational Quality Assurance Manual shall be retained for a period of time as recommended by ANSI N.45.2.9-1974. 6.11 RADIATION PROTECTION PROGRAM 6.11 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 RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each Ugh radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than
'1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection pro:edures (e.g. , Mule PhystcT Technician) or personne' continu-ouslyescortedbysuchindividualsbaybeexemptfromtheRWPissuancerequire-ment during the performance of thei assigned duties in high radiation areas with exposure rates equal to or les ; than 1000 mR/h, provided they are other-
-wise following plant radiation protoction procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with,_p accompani_ed by one or more of the followi m: Qd j gi W otee-h o q
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or.
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the crea and alarms when a creset integrated CATAWBA - UNITS 1 & 2 6 21 Amendment No. 27 (Unit 1)
Amendment No.17 (Unit 2)
.-_ ,_ _ __ __ _ _ __ , _ - _ - . _ _ , , _ . _ . ,,~
g
)
4
. w .
ADMINISTRATI'IECONTR0LJ ,a __. HIGH RADIATI1V Ad*/4 ;Conti utd) , i dose is rect ived. Entry into such areas with this monitoring device may be made ef ts$r the 110se rete levels in tuo area nave been estab-lishtd and perst,nnel have t>een made knowledge 6ble of them; or
- c. An itdividual qualified in radiation protection procedures with .
radiation d'se rate monitoring device, who is retponsible for pro-viding positivt cor. trol.over the activ(ties within the alga and shall perform periodic ~radittion surveillance at the frequency specifled by the 54ti;Meehh nnichin the RWp. =_ fro 3 i e i: a tv e t e-c ? E o 'J ,_,ELa 6.12.2:'In addit l)n to the reouirements of Mecificution 6.12.1,ger 1 areas accessi- , ble to personnel uitb radiation levels greater than 1000 mR/h>at 45 cm (18 in.) > from the radiation source or from any surface which thi_radir. tion penetrates shall be provided uitti locked onors to prevent. ureauthorir.ed entey, and tne keys shall be taaintainec under the.ed.wiristrative control of t5e Shift Superviso! on duty and/or.healthiphysics Aupervision. Doors shall re.ain locked except during ,
. periods eftaccess by personne1'under an approved CWP which shall specify the dose retet favoit in,the isneditte work a,'eas and the maximun allowable stay time for-(ndivicua's in that area. 'In lieu of the stay time specificatioli of -
r the RWP, direct e,r' ret ote (uch as chsed circuit TV cu,uras) continuous sur-
-ve,i' lance may be 'aace wy pe"sonnel qualified in radiation protection proci.dures l' to provide 4 posit've an.usurn control over tne activit es being performed within i
j- the area. For individual high'rsdirtion areas accessible to personnel with rudiation Llevelsi ut greater than 1000 mR/h that are located yithin large arers, such as ' D,WR containuant,' where no s$ncloture pists for purposes of locking, and where no enclosure can be retsona51y'couJtru: tad around the individual nech, that c'ndividua', area shall he batvicaded, c'onspicuously posted, and a flashing ., light shall be activated.as t warning device. .I ' s 6.13 pROCES$40NTROL: PROGRAM (PQ8) m-6.13.1' The PCP shall be appioves by the Commission prior 'to implementation. 6.13.2 iLicensee" initiated ' changes to the PCP: i
- a. Shall-be fubritted to thu hmmission in the Semiannual Radioactive Effluent Relvase Report for tne period in which the change (s) was faadi. This submittal shall contain: -
l
- 1) Sufficier.tly detailed information to totally support the rationale for the change without benefit of additional or !
. supplemental information,
- f 2) A determination that the change'did not reduce the overall. j conformance of the solidified waste product to existing criteria for solid wastes; and .
- 3) Documentation of the fact that the change has been reviewed and _
found, acceptable by the Station Manager 6,- %e. C.hemmm meMen I i CATAWBA - UNITS M 2 6-22
_ _ . _ - - . _ _ _ _ _ -. - - . .. - . _ _ _ _ _ _ - - . _ . . - - _ - _ . _ . . . _ _ _ _ _ _ _ _ - m 6 r
-4 0 ADMINISTRATIVE CONTROLS j 6;13 PROCESS CONTROL PROGRAM (PCP) (Continued)
- b. Shall become ef fective upon review and acceptance by a qualified individual / organization.
6.14 0FFSITE DOSE CALCULATION MANUAL (00CH) 6.14.1 The ODC)1 shall be approved by the Commission prior to implementation. 6.14.2 Licensee-initiated changas to the ODCM: l
- a. Shall be submitted to t.se Commisqion b the Semiannual Radioactive Effluent Release Report for the period in whien the change (s) was
, ande effective. This su)mistal shall contain: .
- 1) Sufficiantly detai' led inforuation to totally support the
, rationale Nr the thange without benefit of additional or supplemental inforsation. Infomation submitted should consist of a pa;kage of +. hose pacet of the ODCM to be. changed with each page nusabered, da*ed, and containing the revision numoer, 1
together with appropriate analyses or evaluations justifying the l change (s);
- 2) A determination tM, the change wi11 not-reduce the accuracy or reliability of done calculations of Setpoint determinations; and
- 3) Documentation of the fact that the change has been reviewed and '
found acceptabl,e by the Station Manage [r . r mil %dia%a Hcd.eci4Q, p t a.nagox . \ .
- b. Shall become effective' uron review and acceptance by a qualified individual / organization. .
6.lb MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RA0 WASTE TREATMENT SYSTEMS
- 6.15 Licensee-initiated major changes to the Radwaste Treatment Systems
-(liqui #,. gaseous, and rolid):
- a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Station Manager. The discussion of each change shall contain:
1)* A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- Licensees may choose to submit the information called for in this Specification as part of the annual FSAR update.
CATAWBA - UNITI 1 & 2 6-23
, , _ _ ...m__ .__, . . _ . . . _ _ __ _._ _ , , __ - _ _ ~ _ _ _ _ . _ . _ _
o o ADMINISTRATIVE CONTROLS , , MAJORCHANGfSTOLIQUID, GASEOUS,ANDSOLIORADWASTETRE/.7dENTjf,TEMS (Continued;
- 2) Sufficient detailed information to totally support t're reason for the change without benefit of additional 9r supplemental informvcion;
- 3) A detailed description of the eouipment, camponen;s, and processes involved and the interfaces with other plant systems;
- 4) An evaluation of the change, which shown the predicten r leaves of radioactive materials in liquid and gaseous a*fluentt una/o-quantity of solid waste that differ from th.'se"previously predicted in the License applic tion ard e,te .itnent theretr;
- 5) An evaluation of the change, which shows d.) expec.ed maximvm
' exposures to a MEMBER OF THE PUBLIC in 1 d5UhdESTRICTED AREA and to the general population that c)ffee h*cm -hi e previc. ly estimated in the License application and amesemsn.J thereto;
- 6) A comparison of the predicted relearts of -adioritive materials, in liquid ar.d gaseous effluents antt in solid ni ;e, to the actual releases for the period prior to when the changes are to be made; ,
- 7) An estimate of the exposure to plert ocerating p rsonnel as a eJsult of the change; and
- 8) Documentation of the fact that the chance was reviewed snd found acceptable by the Statier N 9agerf h Q wier% NmG -- -
m
- b. Shall become effective upon rtview and acceptanes ay a qualified individual / organization.
CATAWBA - UNITS 2 &2 6-24
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i e q
. m t
ATTACHMENT 2
SUMMARY
AND JUSTIFICATION r: e
' Sm
(
e Summary and Justificatlon The changes we are proposing are itemized below, according to the af fected section of Chapter 6 of the Technical Specifications. The majority of the c he.inges are in response to the realignment, re-titling and other restructuring activities which were effactive November 1, 1991. Attachment 4 consists of dr.It revised pages of the Catawba FSAR, Chapter 13, which describes the new organization. Basically, all station activities now fall under the responsibility of the Sito Vice President who can then dologate to the Station Manager or other supervisory staff as appropriate for the activity involved. This transitir,n to the " site" concept accounts for many of the changes in responsibility and lines of authority for the onsite and offsite organizations. Several other proposed changes are in response to Standard Review Plan-(SRP), Section 17.3 which was issued in August, 1990. As discussed with members of your staf f on October 30, 1991, we are in the process of revising the Duke - QA Topical, in which we will implement the guidance in SRP 17.3. These changes, therefore, will provide consistency with both documents. One other proposed change would add an alternative qualification for NSRD members who have extensive experience jn an area of expertise in lieu of a technical degree. All of these changes are suramarized below: Section Summary and Justification of Proposed Changes 6.1.2 This change reflects realignment of authority to t. - site,_ and the larger group of affected personnel who will be at the Site. This change is purely adminis-trative and it can therefore be considered acceptable. 6.2.1 This specification defines the requirements, authority and the current lines of responsibility of the offsite and onsite organizations < As discussed above, . the nuclear site organization centra 11zes the resources needed for safe and efficient operation of the plant. This change reflects the realignment of management authority which is consistent with the recommendation
-of Generic Letter 88-06, and is thus acceptable.
The term " Health Physics" in the last - statement has-been replaced with " Radiation Protection" throughout the Duke System. This is purely an administrative change with no effect on function and should be considered acceptable. 2-1
. 1
. . l l
-6.2.1T In this table the tit 11 of Shift Manager has replaced ;
that of Shift Technical Advisor. The function and i activities of the Shitt Manager encompass and exceed i the requirements of a Shift Technical Advisor, as defined in " Clarification of TM1-roquirements," NUREG 0737. Thus this chango can be considorod acceptablo. l 6.2.2 The term "Hoalth Physics" has boon replaced with ;
" Radiation Protection" throughout the Duko System. l This is purely an administrativo chango with no offect on function and should be considered acceptable.
In (c) the astorisk and associated footnoto have boon doloted because they are no longer nooded. This footnote was inserted during an earlier time when there was only one technician on shif t. We now have amplo shift coverage due to omorgency staffing commitments, making this requiremont obsolete. [ This change would also help sAmplify section 6.2.2 by ollminathg an unnecessary requiremont. This can be ' considered an acceptablo administrativo chango. In (1), the word " station" is used to denote staff who report to the Station Manager and who are engaged-in the " hands-on" operation and maintenance of the station. The common terminology for auxiliary operators is now "non-licensed operators". , In (g), the now titio of Operations Superintendent is editorial and should be considered acceptable. The new titio of Shift Operations Manager does not. represent _ a chango in-function, is_ clearly administrative and thus i should be acceptable. 6.2.3.1- The detetion of the C in CSRG is purely editorial. It 6.2.3.'5 was expressed by tho, respective sito staffs that the term " Safety Review Group", or "SRG", is sufficient at , each- site and that specifying the _ station is unnecessary. This administrativo _ change should be considered acceptabio. 6.2.3.3- The. deletion of the term " Nuclear" in Nuclear Safety ', 6.2.3.5 Assurance is an administrativo chango, which reflects - s the broador scope for this position. This change > should be considered acceptable since it is purely F
~administrativo.
6.2.3.2- With the reorganization, the SRG work unit has increased in sizo due to the inclusion of personnel from- the former on-sito quality assurance group, comprised of quality verification specialists, some of 2-2 O_
i t which are not dogrood. Accordingly wo are proposing to reviso this section to reflect the expanded resources ; of the SRG, and to clearly establish that at least 3 ; persons should moet critorion (1). ; 3 Those changes are editorial and administrativo and do not dirinish or alter the function of tho sito SitG, and thoroforo should be considered acceptable. 6.2.4 The title of Shift Managor (SM) has replaced that of -, Shift Technical Advisor (STA), but its functions and activities encompass and exceed the requiromonts of a ' Shift Technical Advisor, as defined in " Clarification of TMI-RoquAromonts", NUREO 0737. Thus this chango can , be cosa:idered acceptablo. 6.4 This change reflects realignment of authority or responsibility as discussed-above and described in TS ; 6.2.1, and-draft revised CNS FSAR, Chaptor 13.2. The now title of Training Manager reflects the broader concept of sito responsibility. It is administrativo ' in nature and thus should be considered acceptable. 6.5.1.2 It was felt that the Station Manager should be able to dologate his approval authority to the appropriato member of the station supervisory staff in the ovent of his unavailability, since he and his staff have overall responsibility for the safe operation of the plant. a This is an administrativo change only and should be i considered acceptable. 6.5.1.3 It was felt that the Station Manegor should be able to delegato his approval authority to the appropriate member of the station supervisory staff in the event of his unavailability, since ho and his staff havo overall responsibility for the safe operation of the plant. l The key supervisory titles have boon revised to reflect j
'the reorganization and their re-naming. Those changes are purely administrative and should be acceptable.
6.5.1.4 These- changes reflect realignment .of authority or responsibility as discussod' above and described in g proposed TS 6.2.1,.and draft revised CNS FSAR, Chaptor. 13. This change would also make the requirerzent consistent with Specification 6.8.2,.which authorizes the Gonoral Manager, Environmental Services, to review and approve : offsito environmental, technical and laboratory implementing proceduros. Qualifications of the General Manager, Environmental Services can also be found in L '-- 2-3
revised Chapter 13 of the FSAR. Shifting of review responsibility t.o the site from the corporate offiro doos not. alter or diminish the review function, >- administrativo and thus should be acceptablo. 6.5.1.5 It was felt that the Station Manager should be able to delegato his approval authority to the appropriato member of the station supervisory staf f in the ovent of his unavailability, since he and his staf f have overall responsibility for the safe operation of the plant. Tho key suporvisory titles havo been revised to reflect the reorganization and their re-naming. These changes are purely administrative and should be acceptab10. 6.5.1.6 This change reflects realignment of authority or responsibility as discussed above and described in proposed TS 6.2.1, and draft revised CNS FSAR, Chaptor 13. This change also roflects the current philosophy that the-Safety Review Group should report to a management that is indopondent and separato from that of the station and the NSRB. We fool that this is primarily administrativo but also philosophically correct and thorofore acceptable. 6.5.1.7 This change reflects realignment of authority or responsibility as discussed above. and described in proposed TS 6.2.1, and draft revised CNS FSAR, Chapter
-13.
This change'also reflects the current philosophy that the. Safety Review Group should_ report to a management that is independent and separate from that of the station and the NSRB. We fool that this is.primarily administrativo but also philosophically correct and therefore acceptable. 6.5.1.8 These requirements are being relocatop co the Security Plan which will be maintained and implemented by the site- Security Manager. This is consistent with guidance provided by SRP 17.3, which-encouragas the implementing manager to becomo responsible'for the quality of'the plans and implementing procedures. Also, 10CFR 50.54(p) requires an annual review-of security program procedures, with directions for reporting the results to management. We feel this requirement is redundant to the -existing regulation in 10CFR 50.54; therefore this change should be accepted. 2-4
- o. .
1 6.5.1.9 Consistent with 10CFR 50.54(t), the Site Emergency Plan ! provides for the annual review of all procedures. This requirement is being relocated to the Emergency Plan which will be maintained and implemented by the Site Emergoney Manager. This is consistent with guidance provided by SRP 17.3, which encourages the implementing manager to become responsible for the quality of plans
- . and -the implementing procedures. We feel this reqJirement is redundant to the existing regulation in I 10CFR 50.54; therefore this change should be accepted.
6.5.1.10 These changes reflect realignment of authority or responsibility _ as discussed above and described in proposed TS 6.2.1, and draft revised CNS FSAR, Chapter 13. This change is also consistent with Specifications 6.5.1.6 and 6.5.1.7 where the Manager of Safety Assurance assures the review of reportable ovents and special investigations. These changes are administrative and therefore should be considered acceptable. 6.5.1.11 These- changes reflect realignment of authority _or responsibility as discussed above and described in proposed TS 6.2.1, and draft revised CNS FSAR, Chapter
- 13. .
That the responsibility for this review should fall to the Manager of Safety Assurance is consistent with the philosophy expressed for the other activities in this Section concerned with reportable special reviews. This ch .ge is administrative and should be considered acceptable. 6.5.1.12 These - changes reflect realignment of authority _ or
- responsibility as discussed above and described in proposed TS 6.2.1, and draft revised CNS FSAR, Chapter 13.
That the responsibility for this review should fall to L the Manager of Safety Assurance is consistent with our philosophy expressed for the other activities in this Section concerned with special reviews. l The Manager, Human Resources now has responsibility for L the Fire Protection Program. These changes are primarily administrative and thus should be considered acceptable. 6.5.1.13 This change reflects the realignment of authority to 2-5 l
the site. The number 12 is a typographical correction. These changes are clearly editorial or administrative and therefore should be considered acceptable, 6.5.2.2 The naming of Executive Vice President, Power Generation reflects the realignment of reporting authority for the NSRB as discussed in draft revised CNS FSAR Chapter 13 and in the QA Topical Soction 17.3. Thin change is administrative, since the functions of the NSRB are unaffected but we also believe this change is philosophically correct and acceptable. The other pronosed change in this section would increase the p ' of qualified individuals from which candidates coulo be appointed to independently review operational phase activities. The requirements for those who operate the plant are at least this flexible. The appointment would be subject to the approval of the Executive Vice President, Power Generation. This proposed change is not directly related to the Duke reorgani::ation or the requisite revisions to our licensing-documents. If its consideration might slow down the review of all other changes in this chapter, we would prefer tc consider it separately in another submittal.
;6.5.2.3 These changes reflect realignment of authority or responsibility as discussed above and - described in proposed TS 6.2.1, draft revised CNS FSAR, Chapter 13, and the revised QA Topics 1 Report.
The use of the term site" assures the continued independent' nature of the NSRB. 6.5.2.6 This change reflects the renaming of the Department, the function of which is unchanged. This administrative change should be considered acceptable. The "12" corrects a typographical error and is purely editorial.- S 5.2.9 We are applying here the broader term " site" to reflect all those activities associated with the station, not those that are only specific to the operation of the unit. The term " station" in (b) is consistent with its use in Specification 6.2.2(f) and implies those people reporting to the Station Manager, responsible for operation and maintenance of the unit. These changes are administrative and do not alter the function of the 2-6 V * * --v- i ,my ., .-- , -
--,,-----w.-r--g.--ye v , emw. ,- --3-.-
< NSRB organization and therefore should be considered c.cceptabic.
Audit frequencies aro being deleted here but in the revised QA Topical we are preparing the following statement, using SRP 17.3 guidance on planned and periodic assessments scheduling and resource , allocation:
" Audits of selected aspects of operational phase activities are performed with a frequency commensurate with safety significance and in such- a manner as to assure that an audit of all safety related functions is completed within a period of
.two (2) years. The audit system is reviewed periodically and revised as necessary to assure coverage commensurate with current and planned activities."
The naming of Executive Vice President, Power Generation reflects the realignment of reporting authority for the NSRB as discussed in draft revised CNS FSAR Chapter 13 and in the QA Topical Section 17.3. This change is administrative, since the functions of the NSRB are'unaf f acted but we also believe this change is philosophically correct and acceptable. These changes do not alter the function nor diminish the. quality of the Audit Program. Therefore, they should be considered acceptable. 6.5.2.10 These changes reflect ~ realignment of authority or responsibility as discussed above and described in proposed TS . 6. 2.1. These reporting requirements to Senior Management arn also discussed in the revised QA Topical Report in Section 17.3.3 "Self Assessment".
'These changes are administrative only and therefore are acceptable.
6.6.1 These changes reflect realignment of authority or responsibility as discussed above and described in proposed TS 6.2.1, and draft revised CNS FSAR, Chapter
.. 13.
The key supervisory titles have been revised to reflect the reorganization and their re-naming.. The changes are purely administrative and should be acceptable. 6.7.'1 The changes- in (a) and (c) reflect realignment of authority or responsibility to the site as discussed above and. described in TS 6.2.1, and draft revised'CNS 2-7 ll [_.
. .~ _ . . _ _ , . _ . ~ - _ .
0 FSAR, Chapter 13. Operations Superintendent in (b) is simply renaming of the position. These changes aro administrative and therefore shou?.d be considered acceptable. 6.8.1 (c) and- (d) sto being removed from the Technical Specifications and relocated to security Plan and Emergency Plan, respect.1vely, bocasso the procedures covering these activitwa are the responsibility of the ' Site Emergency Planner and the Site Security Manager and, as such, are included J n their respectJ /e site Plans. This is consistent with guidance provided in revised Standard Review Plan Section 17.3, which encourages the delegar, ion of authority to the implementing manager. This change will simplify this specification and is adrainistrative. I t- should be considered acceptable. 6.8.2 Review and approval of procedures was changed to re-flect realignment of authority or responsibility, since some proceduras no longer f all under the responsibility of the Station Manager (o.g., fire protection, perfor-mance procedures, emergency pinnning). The Site Vice President can delegate to the implementing manager, consistent with the revised QA Topical Report and guidance given in SRP 17.3, which encourages the delegation of authority to the implementing manager. The General Manager, Environmental Services, now has responsibility for all of.fsite environmental activities. The term " Applied Science Center" is no longer correct and is therefere unnecessary. All of these changes.are administrative and as such should be considered acceptable. 6.8.3 These changes in (c) reflect realignment of authority or responsibility as discussed above and in proposed TS 6.2.1, and draft revised CNS PdAR, Chapter 13. These changes also simplify the specification and make it consistent _ with revised 6.8.2. These changes are administrative and should be considered acceptable. l 6.12.1- The term " Health Physics" has been replaced -with
" Radiation Protection" throughout the Duke System.
Likewise, the " Station Health Physicist" has been ronamed. These are purely administrat ivo changes with no effect on function and should be considered acceptable. 6.13.2 This change a110ws the Chemistry Manager to revleu 4.ad approve revisione. This is consistent with Sta non d 2-8 l
s r Review Plen SRP 17.3. which encourages the dologation ', of authority to the implementing manager. It also allows additional flexibility in the case where one or . the other is unavailable. This is administrative and
- should be considered acceptablo.
6.14.2 -This.chango allows the Radiation Protection Manager to review 'and approve revisions to ODCH. This is consistent with Standard Review Plan FRP 17.3. which ; oncouragos the delegation of authority to the implomonting manager. It also allows additional floxibility in the case where one or the other is unavailable. This is administrative and should be i considered acceptablo. 6.15(a)8 This change allows the chemistry Manager, who has lino responsibility over radj'aogical offluent controls, to review and approvo changes to the Radwaste Troatment System. This is consistent with Standard-Review-Plan SRP'17.3. which encouragos the dologation of authority to the implomonting manager. It also allows additional flexibility in the case whero one or the other is unavailable. This change is administrative and should-be corisidered acceptable. P 4 e i 2-9 i
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" -, ,-+ - ., ,,. , _ , , , , . _ , _ _ _ , _ _
- .- . - - - - - _ - - - ~ - - . - - . ... - - ~r Analvais of Significant Hazards Consideration:
As Rerquired by 10CFR 50.91, this analyr,is is provided concerning
- whether the proposed amendments involve significant hazards considerations, as- defined by 10CFit 50.92. Standards for ;
determination that a proposed amendment involves no significant hezards considerations are if operhtlon of the facility in accordance. with - the proposed amendment would not: 1) involve a Bignif1 Cant increase in the probability or consequences of an accident previously evaluated; or 2) create the possibility of a new or different kind of accident from any accident previously evaluated;-or 3) involve a significant reduction in a margin of safety. l l The proposed amendments would not iravolve a significant increase _ in ! the probability or consequences of a previously evaluated accident. Nor would they create the possibility of-a new or dif ferent kind of accident from any accident previously evaluated.
~
The changes do not have any impact upon the design or operation of plant equipment; .thereforo,-they cannot serve to initiate a new type of accident.
- The proposed amen'dments would not involve a reduction in a margin
- of saf ety. The-changes would not impact the design or operation of any plant systems or components, j Based upon the preceding analysis, Duke Power Company concludes that the proposed amendments do not involve a Significant Hazarde Consideration, i
l-l 3-1 l
.ig-, ..
F T ATTACHMENT 4 CATAWBA FSAR CHAPTER 13 REVISED PAGES
+
, . Chapter 13. Conduct of Operathms Catawba Nuclear Station
-CHAPTER 13. CONDUCT OF OPERATIONS I
E l 13-1
4 s .*- . 13,1 Organisational Structure. Catanba Nuclear Station 13.1 ORGANIZATIONAL STRUCTURE 13.1.1 CORPORATE ORGANIZATION 1 The corporate structure of Duke Power Company is shown in Figure 131 on page 1310 and i Figure 13 2 on page 1311. 13.1.1.1 Corporate Functions, Responsibilities and Authorities Duke Power Company has over 75 years of experience in the , ign, construction and operation of electric generating stations. As of January 1,19S8 Duke operated eight conventional steam electric stations with a capacity of 6,428 MWe, three nuclear sicam electric stations with a capacity cf 7,054 MWe, 25 conventional hydroelectric stations with a capacity of 842 MWe, four pumped storage hydroelectric units with a capacity of 610 MWe and combustion turbine peaking units with a capacity of
$99 MWe, for a total system capacity of 15,553 MWe.
Company involvement in nuclear power began in the early 1950's with various personnel r:cciving nuclear training. Selected personnel have been involved full time in nuclear projects sim ihe trad 1950's. Duke participated in the Carolinas Virginia Nuckar Power Associates (CVNi'A), which resulted in a 17,000 kWe nuclear steam-cleckic unit at Parr, South Carolina. Thh unit, the Carolinas Virginia Tube Reactor (CVTR), produced eleci , fy over the period 1963 to 1967 as part of a five-year operating research program. Duke's three unit Oconcc Nuclear Station began operation in 1973, the two unit McGuire Nuclear Station bey.n operation in 1981, and the two unit Catawba Nuclear Station began operation in 1981. A a result of these and other assignments, maay engineering personnel in the Duke organization have had prior nuclear experience as well as extensive experience in the power field. Various departments within the Company have responsibility for design, construction, quality assurance and operation of each nuclear station. Duke contracts with a nuclear steam supply system (NSNS) vendor for the design and manufacture of the complete N5SS. The NSSS vendor also provides technical consultation in areas such as construction, testing, startup and initial fuct loading. Duke's corporate functions, responsibilities and authorities for quahty assurance are addressed in Topical Report, DUKE 1A. 1 The Chairman of the Board and Chief Executive Officer has overall responsibility for corporate functions l_ involving planning, design, construction and operation of the Company's generation, transmission, and 1 distribution facilities, as well as other stafi functions. 1 Line responsibilities relative to Nuclear Generation are delegated through the Executive Vice President 1 Power GeneraGon Group, to the Senior Vice President, Nuclear Generation. 13.1.1.2 Organization for Design and Construction 1 Effective November 1,1991, Duke reorganized to create the Power Generation Group, which includes the i Nuclear Generation Department. Separate organizations for &<ign and construction ceased to exist. i 13.1.2 OPERATING ORGANIZATION l REY:(DRAIT NOV 1991) 13-2 l
-.. . - . - - -.- - -. . . - ~
, c _13.1- Organisational Structure : Catawba Nuclear Station
. n
!= 13.1.2.1 Nuclear Generation DepMtment Organization j i
- l- ~ Duke's Nuclear Generation Department._ headed by the Senior Vice President, Nuclear Generation, has - l
.1; - corporate responsibility for overG nuclear safety, as established by Technical Specifications. Reporting to 1 the Senior Vice President i< a Vice President for each nuclear site, and the General Atanager, Nuclear ,
1 Senices.- l l
! Tae Nuclear G;neration Department Organization is shown on Figure 13-3 on page 1312.
]
1 -13.11.2' Nuclear Site l l 1 13.1.2.2.1 Site Organization
]
!- The nuclear site organization centralizes the resources for safe and efficient nuclcar plant operations under 1 a vice president at the nuclear site.
I ne Vice President of Catawba Nuclear site has the responsibility for overall plant nuclear safety as
-1i ; established by Technical Specifications. The site statT is fully capable and equipped to handle all 1 situations intohing safety of the station and public. The Nuclear Station staff is shown on Figure 13-4 l= _ on page 13-13.
1 As established by the Duke Quality Assurance Program Topical Report, Duke 1 A, anyone involved in
-1 quality _ aethities in the Duke organization has the authority and responsibility to stop work if they 1 . discover deficiencies in quality.
1, 13.1.2.2.2 Personnel Functions, Responsibilities and Authorities 1 1 The functions and n:sponsibilities of key site supervisory staff are described in the succeeding paragraphs. 1 (a)- Station Afanager 1 The. Station hianager reports to the Vice President, Catawba Site and has direct responsibility for
- 1, - operating the station in a safe, reliable and etlicient manner. Ile is responsible for protection of the l' station stafT and the general public from radiation exposure and/or any other consequences of an accident
- 1i at the station. -lie bears the respcmsibility for compliance with the facility operating license; The Station Atanager or his designee has the authority to approve and issue Station Directives and procedures.
1 . (b) Operations Superintendent , 11 The Operations Superintendent has the responsibility for directing the actual day-to-day operation of the ; 1- station. In the event of the absence of the Station Stanager, the __ Operations Superintendent, if so 1 _ designated, assumes the responsibilities and authority of the Station Nianager. p, 1 .(c) Shift Operations .>.lanager
'I ne Shift Operations Atanager is responsibility for directing the activities of the on-shift licensed and.
- j. 1 -- non-licensed operating personnel.
1 (d) Shift Supervisor i 11 - A Shift Supcnisor is resp <msible for the actual operation of the station on his assigned shift. lie directs ! -1 - the aethiues of the operators on his shift and is cognizant of all maintenance actidty being performed l REY: (DRAIT NOV 1991) 13-3 l- .
, .- - . . - - - ~ . - - - - - ~ . . . .. - . -- .- .
k
.A;
, n. . 13.1: Organizational Structura Catawba Nuclear Station"
-1 while he is on duty. The Shift Supenisor on duty has both the authority and the obligation to shut down 1- a unit if,in his opinion, conditions warrant this attion.
-(e) Assistant Shift Supervisor--
~1-21- An Assistant Shift Supenisor assists'the Shift Supenisor in operation of the station on his assigned shift.
1- - The Assistant Shift Supenisor on duty has both the authority and the obligation to shut down a unit if, 1 in his opinion,' conditions warrant tids action.
?! . (f) Shift Manager i A Shift Manager provides evaluation and assessment of both normal and unanticipated transients. '
1 (g) Reactor Operator
-1.
- A Reactor Operator is responsible for the actual operation.of a Unit on his assigned shift. The Reactor 1L Operator has both the autb(>rity and obligatiors to shut down a unit if, in his opinion, conditions warrant ;
1-- this action.- 1 - (h) Nuclear Equipment Operator
--.1 - .A. Nuclear Equipment Operator is responsible for the operation of equipment outside of the Control
- 1. Room.
~1 .(i) Radiation Protection Manager 2
! ' The Radiation Protection Manager has the resp (msibility for conducting the radiation protecJ.m program.
- 1. IIis duties include the training of personnel in use of equipment, contml of radiation exposure of 1- personnel, continuous deteimination of the radiological status of the station, surveillance of radioactive El T wr.ste disposal operations, condu'eting the radiological emironmental monitorina, program and maintaining:
11- all acquired records. 'lle has direct access to the Station Manager in matters concerning any phase of-1 -- radiological protection. The Radiation Protection Manager also has direct support as required from the
- 1 : Chemistry / Radiation Protection Manager in Nuclear Senices and his staff.
1l L (j)- Chemistry Manager The Chemistry Manager is responsible for overall chemistry and radiochemistry requirements, with special 1_ emphasis on primary and secondary system water chemsitry.
;ls (k)l Mechanical Superintendent p
- 1; The Mechanical Superintendent has responr.ibuity for maintenance of mechanical equipment.
h I (1) I&E Superintendcat n -- . E
;1- %e 1&E Superintendent has- responsibility for maintenance of electrical equipment, instrumentation,-
[- J controls, and computers.
- 1 (m) Work Control Superintendent o-r e
REY: (DRAIT NOV 1991) - 13-4
, ,~ - - .. .- - - - . - - . - . - - . - - - - - - - - . . - _ .
3
-.; ? ,
, . _13,1 Organtiational Structure Catawha Nucicar Station
~
~ 'l The Work Control Supuintendent manages the station's efforts to support Catawba's Nuclear Station's-l1) - operational and outage activities through the coordination, development, shifi and outaga management of -
11: : a timely and effective integrated station schedule.
.1= (n) Safety Assurance blanager --
1 The Safety Assurance Manager is responsible for directing the activities of Environmental and NRC 1J Regulatory Compliance, Safety Review, Emergency Preparedness, INPO Coord'nator and IIPES. 1: (o) Compliance 1 -- The Compliance lead has responsibility for coordinating station interfaces with regulatory agencies and for , I providing review of appropriate station technical matters.
.1 (p) lluman Resources Manager
- 1- ' Die iluman Resources Manager is responsible for coordination of site administrative functions including ie clerical, document control, safety, fire protection, training ano scurity.
-g-L13.1.2.3 Shift Crew Composition
..The normal operating shift crew consists of a Shift Supenisor, an Assistant Shift Supen or for each unit, I a Sluft Manager (ivho fulfills the STA role), and . appropriate licensed and unlicensed operators. In-
' addition, a radiation protection technician is on site at all times when there is fuel in a reactor and a rad! chem technician is onsite at all times when a unit is being operated in Modes 14.
11 13.1.2.4 = Nuclear Services Organization l' The Nuclear Senices organization provides corporate oversite and specific technical senices to all Duke l- Nuclear sites. LThis~ organization is headed by the General Manager, Nuclear Senices. The organization LI _ chart is shown on Figure 13-5 on page 13-14. The function and responsibilities are described in the IL - succeeding paragraphs. I1 ? 1; Nuclear Engineering _ i 1- This orgardzation has the responsibility for safety analysis, probabilistic risk assessments, reactor core
'l' design,- ut-of-core fuel management, core thermal hydraulic design, fuel fabrication, and failed fuel:
_ analysis
- 1 2. Engineering / Maintenance Support
- I; - This organization provides operating support to all Duke nuclear sites with an emphasis on generic
. 10 ' programs and the promotion of consistancy. Support is provided for the areas of Civil and Electrical 1 Engineering,' Mechanical and- Instrument & Electrical (l&E) Maintenance, and Mechnical and 1 . Electrical Materials Procurement Engineering.'
l 1 - 3. Safety Assurance ,
- 1. This organization provides oversight and support to assure safe nuclear station operation and-
-1: compliance with regulatory requirements Work Units include Nuclear Licensing Senices, Operational
' Event Analysis Emergency Planning and QA Technical Services. 1 l_ 4. Ope ations, Performance, and Automation l'
i-h ' RIiVi(DRAl'I' NOV 191) 13 5 L v .
9 f ic .(
-.,i 13,l' Organizational Structure Catawha Nuclear Stathm i
-I< This ' organization provides senices and leadership which support, and supplement station personnel 1c efforts as they relate to' the operation of the station. Primary roles include support of long term -
1- development of new programs, policies and technology in the areas of reliability improvement, generic
- I operating issues, system and component performance, and automation projects; as well as suppon for 1 the development of projects that are not feasible or economical endeavors for the individual 1 station.
I S. Nuclear Technical Senices 1 This organization is responsible for providing oversight and technical support in the areas of : 1 chemistry, radiation protection, radwaste and radioactive materials control. It also determinesand 1 .maintairaall dosimetry records for Duke Power nersonnel. 13.1.3 QUALIFICATIONS OF STATION PERSONNEL 1 The qualifications of personnel in the site organization aie in accordance with Section 4 of ASSI
- NIBJ-1971; " Selection and Training of Nucicar Power Plant Personnel *, and are ir accordmce with Regulatory Guide 1.8 (Rev.1) with the exception of those for the Radiation Protection Ahmager in P'u1 C '
1 of Regulatory Gt.ide 1.8. . Qualifications of key site persomel are available fot inspection on site. The RPhi-(Station Radistion Protection Nianager) shall have a bachelor's degree in a science or engineering subject or the equivals nt in experience, including some formal training in radiation protection, and shall have at least firiyears of profeuional experience in applied radiation protection of which three years shall be in applied radiation protection work in one _of Duke Power Company's nuclear stations. A qualified individual who does not meet the above requirements, but who his demonstrated the required radiation protection management . capabilities and has professional experience in applied radiation protection work at one of Duke Power Company's multi unit nuclear stations, may be appointed to the position of Station Radiation Protection Nianager by the station Nianager, based on the recommendations 1 of the Nuclear Senices LChemistry/ Radiation Prote< tion Atanager and as approved by the site Vice - 1 President. An individual'who temporaruy replaces the RPSI shall have a bachelor's degree in a science or engineering subject or the equivalent in experience and shall have at least two years experience, one of which shall be nuclear power plant experience. Six months experience shall be on' site. . Replacement personnel for positions at the station are fully trained and qualified to fdl their appointed - positions. 13.1.3.1 Minimum Qualification Requiremer'ts-The ndnimum qualification requirements for station personnel are outlined in the succeeding paragraphs.
- 1. Station N1anager i The Station Alanager shall have a minimum of ten years of responsible nuclear or fossil station -
experience, of which a minimum of three years shall be nuclear station experience. A maximum 'of four years of the remaining seven years of experience may be fulfdled by academic training on a one-for-one, time basis. To be acceptable, this academic training sball be in an engineering or scientific - 1 field generally- associated with power product,on. The Station hianager shall have acquired the experience and trc.ining normally required for examination by the NRC for a Senior Reactor Operator license, whether or not the examination is taken. I 2. Operations Superintendent p i
- REV
- (DRAIT NOV 1991) 13-6
. . i
.3 ,
, 13,1 Organizational Structure Catawba Nuclear Station 1 The Operations Superintendent shall have a minimum of eight years of responsible nuci ar or fossil station experience, of wh:ch a minimum of three years shall be nuclear station no.n.ence. A maximum of two years of the remaining five years of experience may be fulfilled by academic training, I or related technical training, on a one for one, time basis. The Operations Superintendent shall hold or have held a Senior Reactor Operator license.
1 3. Safety Assurance hianager i The Safety Assurance hianager should have a minimum of eight years of responsible nuclear or fossil station experience, of which a minimum of one year shall be nuclear station exp ience. A maximum of four years of the remaining seven years of experience should be fulfilled by satisfactory completion of academic training. 1 4. Alechanical Superintendent' 1 The Alechanical Superintendent shall have a minimum of seven years of responsible nuclear or fossil station experience, or applicable industrial experience, of which a minimum of one year shall be nuclear station experience A maximum of two years of the remaining six years of experience may be fulfilled by satisfactory completion of academic or related technical training on a one-for one time 1 basis. The Niechanical Superintendent should also have non-destructive testing familiarity, craft knowledge, and an understanding of electrical, pressure vessel and piping codes. 1 i Shift Ope.ations Nianager i A Shift Operations Nianager shall have a minimum of a high school diploma, or equivalent, and four years of responsible nuclear or fossil station experience, of which a minimum of one year shall be nuclear station exprience A maximum of two years of the remaining three years of experience may 1- . be fulfilled by academic or related technical training on a one for-one, time basis. A Shift Operations 1 hianager shall hold a Senior Reactor Operator license. 1 1- 6. Chemistry Nianager 1 The Chemistry Alangaer shall have a minimum of five > cars of expenence in chemistry, of which a minimum of one year shall be in radiochemistry A minimum of two years of this five years of experience should be fulfilled by academic or related technical training. A maximum of four years of tha five years of experience may be fulfilled by academic or related technical training. I 7. . Radiation protection hianager See Section 13.1.3, " Qualifications of Station personnel" on page 134 I 8. Complian-1 The Compliance lead shall have a minimum of live years of technical experience, of which a minimum of one year shall be nuclear station experience. A maximum of four years of this five years experience may be fulfilled by related technical or academic training. I 1 9. I&E Superintendent 1 The I&E Superintendent shall have a minimum of five years of experience in instrumentation and control of which a minimum of six months shall be in nuclear instrumentation and control. A muumum of two years of this five years of experience should be fulfilled by academic or related technical training. A maximum of four years of this five years of experience may be fulfilled by academic or related technical training. I REY: (DRAIT NOV 1991) 13-7
=,
a
, < 13.1 Organizational Structure Catawba Nuclear Station 1 10. Shift Supenisor 1 A Shift Supenisor shall have the same qualifications as the Unit Manager.
I 11. Assistant Shift Supenisor An Assistant Shift Supenisor shall have the same qualifications as a Shift Supervisor. I 12. Shift Manager 1 ' A Shift Manager shall have a bachelor's degree or equivalent in a scientific or engineering discipline and two years of responsible nuclear power plant experience accompanied by an overall knowledge of the plant. I 13. Operators Operators to be licensed by the NRC shall ha e a high school diploma, or equivalent, and two years of nuclear or foss3 station experience, of which a minimum of one year shall be nuclear statior. experience. In order to be acceptable for full responsibility in a job, they shall hold a Reactor Operator license. Operators, whether or not they are to be licensed by the NRC, should have a high school diploma, or equivalent, and should possess a high degee of manual dexterity and mature judgment. 1- 14. Technicians Teclaticians in responsible positions (i.e., individuals who direct the actisities of others and who are responsible for the activities they direct) shall have a minimum of two years of experience in their specialty. These personnel should have a minimum of one year of related technical training in addition to their experience. I 15. Maintenance Personn.,1 Maintenance personnelin responsible positions (i.e.. individuals who direct the activities of others and who are responsible for the activities they direct) snall have a minimun. of three years of experience in e se or more crafts. . They should possess a high degree of manual dexterity and ability, and should be capable of learning and applying basic skills in maintenance operations. I_ 16. Work Control Superintendent i The Work Control Superintendent should have a minimum of eight years of responsible nuclear or fossil station experience, of which a minimum of one year shall be nuclear station experience. A naximum of four years of the remaining seven years of experience should be fulfilled by satisfactory completion of academic training. O REY: (DRAFT NOV 1991) 13-8
, . 13.1 Organizational Structure Catawba Nuclear Station 13.1.4 TABLES 1 Table 13-1. To be provided 0 Table 13-2. Deleted Per 1990 I? plate REY: (DRAFI' NOV 1991) 13-9 h
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. _ . . . _ . . _ . . ~ - - - _ _ , .. _ . _ _ _ . _ _ . . . . , _ . . _ . . . . . . _.
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_j 13.1 Organizational Structure - Catawba Nuclear Station --
- p. _,
13.1.5 FIGURES 4 1 Chairinan- & President Vice Chair. Executive VP Executive'VP Executive VP Corpsrate Group- Customer Group Power Generation General Counsel 4- Group-
-1 Figure 13-1.
I Duke Power Corporate Organization -
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. -* 13.l; Organizad_tal Structure . Catawba Nuclear 5 station
-4 GENERAL MANA.GER NUCLEAR SERVICES . ;
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, , N'JCLEAR ENGIt.EEMING/ SAFETY OPERATIONS, NUCLEAR TECH ENG7NEERING 'hAIHTTNANCE ASSURANCE PERFORMANCE SERVICES .,
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,;T l I ligure 13-5. ,
1- Nuclear &nica Organtiation l s
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Catawba Nuclear Station i 13.2 TRAMNG a . M ' 13.2.1 GENERAL PROGRM DEDCRIPTiCN o The principal objectiu of toe Duke Potver Compny H*nployee Training and Qualification System m (ETQS) is to asrxe ich p.uficiency of all mation pmonnel involved in safety related work through
'eticctive training an6 TA.lification. 1hr syticit. is den, sed tu accommodate future growth and meet .
. commitmenh, to and cdmply mth appt'catb established .cgulatiom and accreditation standards.
; . Qualification is indicated by turressful completion of presciibed training, demonstration of the ability to perform asngned work er tasks cotnpetemly and wten; requered by regulation, maintaining a current and valid license issued by the arney estabhshing the requirements.
I- ' Cmhhn w rE 1 b Overall responsibiliiy for training and qualificatio.1 of persomiel rests with l the Vice President, Generation-- 1 %t rices. The 4 ice-PresidentrCatawba-sitWnpensible for-th-conduct-of On The-Job-trainine-and i , ,qvalification-chocksutt for-their-nspective perwnel .Canmunication-of-training-and-qualification-
-needsr chang *in regulatcry te quireme-tscand evaluation feedback-on4he effectiveness of the training.and
;- . qualification programs are prmided to T echnical Training (T)) of the Generation Services DepartmentL a -
1 TT-provide the-analysisrdesigncdevelopment;-implementationrand evaluatiorrof1 raining and-
.d '
- 1- .qualificatioceprogamtirsupport of personnel performing tasks in-the nuclear stationsJurthermor41T- (
insueutation traming-prortams-meet-orxxceed-au-facility LicensingrFSARr-Administration-Policy or-other reguktory_ requirements-Training- is designed, developed and implemented acccrding to a systematic approach to training. Employees are provided with formal training to establish .the knowiedge foundation and on the job training t . develop work performance skills. Continuing training is provided, as required to maintain proficiency in these knowledge and skill components, and to provide further employee development. m8 'l l The Employee Trammg and Qualifications Program is designed to prepare initial and mplacement station
, - personnel for safe, reliable and efficient operation of the nuclear facility. The program is intended to meet -
or exceed INPO accreditation criteria and regulatory requirements.- g
' Appropriate training for personnel of various training and experiences backgrounds is providedb The level .
at which an employee initially enters the training and qualification system for the particular area, is - determined by an evalurtion of the employee's past experience and level of ability. 13.2.1.1 Regulatory Requirernents The applicable portions of the NRC regulations, regulatory guides, and reports listed below will be used in providing guidance in plant staffing and training.
.10CFR PART 50 " Licensing of Production and Utilization Facilities"
. L10CFR PART 55 " Operators Licenses" including Appendix A 10CFR PART 19 " Notices, Instructions and Reports to Workers: Inspections
. Regulatory Guide 1.8 JPersonnel Selection and Tnining"
. NRC " Operator Licensing Guide *, NUREG-0094, July 1976
. " Utility Staffing and Trammg for Nuclear Power", WASH.ll30, USAEC Revised 1973 j' . N.UREG 0654,fTMI - Related Requirements for New Operating Licenses" Regulatory Guide 8.2 " Guide for Administrative Practices in Radiation Monitoring *
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13.2 Tralnlig . Cettwba Nuclear Stttion r.. 13.2.4 TRAINING PROGRAM EVALUATIONS a Tra;ning and qualifications activities are monitored by designated station personnel, the Production Traidag Se: vices staff, and by ETQS Working Groups. The Quality Assurance Department audits the station Employee Trmning and Qualification System. In addition, trainees and vendors may proside input concerning training program effectiveness. Stethods . utilized to obtain this information are suneys, questionnaires, performance appraisals, stJ. evaluation, overall training program effectiveness evaluation instruments, ete Dequer.tly conducted classes are not evaluated each time. However, they are routinely evaluated at 4 frequency sufficient to determine program chective%ss. '.ources of evaluations are ProduWon fraining Senices, General Office Technical staff groups, Employee Training and Qualifications Working Groups and outside vendors. Evaluation information may be collected through: a verification of program objectives as related to job daties for which intended;
- periodic Working Group Program evaluations:
= testing to determine student accomplishmer of objectives; a student evaluation of the instruction;
- supenisor's evaluation of the trainee's performance after training on the job; and .
supenisor's evaluation of the instruction. The performance and competency of Licensed Reactor Operators and Senior Reactor Operators is evaluated as described in the Duke Power Company. Employee Tratmng and Qualification System Standard No. 2306.0 " Periodic Training Licensed Operator Requalification* dated effective Starch 1,1987, as reviewed and approved by the Nuclear Regulatory Commission, January 28,1987. Unacceptable individual performance is transmitted to the appropriate group Superintendent. 13.2.5 TRAINING AND QUALIFICATIONS PROGRAM DOCUMENTATION -
& he ,s3 Me~yn Records are maintained on each employee's participation in training activities. It is -PmdnewTraining-
-Sm se responsibility to see that traming records ofindividuals are accurate and retrievable.
Documentation associated with Licensed Operator training and Requalification is maintained sccording to the requirements established by the Duke Power Company-Employee Traming and Qualification System Standards No. 2303.0 " License Preparatory Reactor Operator Program," No. 2304.0 " License, Prepara-tory Senior Reactor Operator Program," and No. 2306.0
- Periodic Trauung Licensed Operator -
Requalification* dated effective March 1,1987, as reviewed, and approved by the NRC ou January 28,
- 1987. Records shall be retained as per Station Technical Specifications.
13-21
13.4 Review and Audit Catawba Nuticar Station 13.4 REVIEW AND AUDIT In matters of nuclear safety, both onsite and off site review of station startup, operation, maintenance and technical matters is performed. Off site review is performed by the Nuclear Safety Review 130ard (NSRil) whereas onsite review is perfonned by the Nuclear Station Safety Review Group (SRG) and by other designated, qualified individuals. 'Ihis review process commences at least six months prior to the initial operation of a station, so as to include preoperational testing and checkout of the station. Guidance in the development of the review program for test and operation is derived from ANSI N18.7-1976, Administrative Controls for Nu:lcar Power Plants. 13.4.1 ONSITE REVIEW Qualified individuals from the station supervisory stati are assigned to review procedures, procedure changes, Technical Specifications changes and plant modificatians involving nuclear safety. These 1 individuals are previously designated to perform these reviews. The final approval of the above reviews is I by the Station Manag r or other senior station management. In addition, for each review conducted, a determination is made as to whether or not additional cr.,ss-disciplinary review is necessary, if concluded that it is necessary, the additional review would be performed by the appropriate designated station review personnel. Incident investigation including 1.ERs and special re.iew:, une performed by the SRG or other designated qualified ind;viduals. 13.4.2 INDEPENDENT REVIEW 13.4.2.1 Offsite The Nuclear Safety Review floard (NSRB) is estabhshed to venfy that the operation of a station is performed it a safe manner consistent with Company policy, approved operating procedures and license provisions; to review important proposed station modifications, tests and procedures; to verify that reportable occurrences are promptly investigated and corrected in a manner which reduces the probability of occurrence; and to detect trends which may not be appar.:nt to a day-to-day observer. The Board I reports its findings and recommendations to the Executive Vice President, Power Generation, and as I required by Technical Specifications. The membership of the NSRil collec:ively ins the competence required to review problems in the following areas: Nuclear power station operations. nuclear engineering, chemistry, radio-chemistry, metallurgy, instrumentatiori and control, radiological safety, mechanical engineering and electrical engineering, administrative control and quality assurance practices. The NSR3 is composed of not less 0 than five persons, of whom no more than one is a member of the station organization. For review and 0 audit of 'lechnical Specifications, a quorum shall consist of five members and must include either the chairman or h's designated alternate. Fermal meetings are held at least semi-annually. More frequent meetings are held if necessary. 1 Minutes of meetings are prepared and distributed to the Executive Vice President, Power Generation, and 1 as required by Technical Specifications. The NSRil has the following general responsibilities: 1 l REY:(DRAIT NOV 1991) 13 23
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- 13A Review and Auait Catanba Nuclear Station
- 1. Review aafety evaluations for (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provisions of 10 CFR 50.59 (a) (1) to venfy that such actions did not constittee as tinreviewed safety question.
- 2. Review proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
- 3. Review tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
- 4. Review proposed changes in Technical Specifications or Facility Operating Licenses.
- 5. Review violations of applicable statutes, codes, regulations, orders, Technical Specifications, licenu requirements, or ofinternal procedures or instructions having nuclear safety significance.
- 6. Review significant operating abnonnalities or deviations from normal and expected performance of station equipment that affect nuclear safety.
- 7. Review incidents that are the subject of non routine reports submitted to the Commission.
I 8. Review Quality Verifications Department audits relating to station operations and actions taken in
. response to these audits.
Audits of station activities are performed by or under the cognizance of the NSRB. These audits encompass such items as:
- 1. The conformancy pf station operation to provisions contained within the Technical Specifications and applicable Facility Operating Lit.ense conditions.
- 2. The performance, training ar_. qualifications of the station staff.
- 3. The results of actions taken to correct deficiencies occurring in equipment, structures, systems or methods of operation that affect nuclear safety.
- 4. The perfonnance of activities requind by the quality assurance program to meet the criteria of Appendix B to 10 CFR 50.
- 5. The station emergency plan and implementing procedures
- 6. The station security plan and implementing procedures.
13A.2.2 ONSITE The Nuclear Station Safety Revi:w Group (SRG) is established for the purpose of independently examining and making detailed recommendations to management on plant operating characteristics, NRC issuances, Licensing Information Advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety; performing independent reviews and audi:s of plant activities including maintenance, modifications, operational problems, and operational analyses, and aiding in the establishment of progranunatic requirements for plant activities; verifying that plant operations and maintenance activities are performed correctly and that human errors are reduced as far as practical by mamtaining necessary surveillance; and performing incident investigations as assigned by the station organization, and preparing required reports. The SRG will advise the station and corporate management, and the Director of the NSRB, on the overall quality and safety of plant operations. A-1 monthly summary report of the SRG activities will be forwamed to the Station Safety Assurance 1 Manager, who will in turn advise management. Other information on the conduct of operation of the SRG is provided in the SRG Charter for Nuclear Stations and SRG Operating Procedures. The Nuclear Station Safety Review Group (SRG) is an independent review group located onsite. Itis composed of a permanent chairman and a muumum of four rotating members appointed for a mmunum 1 of six months. The members will be chosen from among experienced station personnel, Nuclear REY: (DR AFI' NOV 1991) 13-24
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13.4 Revi6w and Audit Catawba Nuclear Station
! Generation and other departm:ntal technical groups in the General Oflice, and will be multidisciplined with expert.. in -the areas of instrumentation, maintenance, operations, and technical services (e.g.,
1- radiation protection, chemistry / radiochemistry, radwaste, etc.). Qualifications of all members are stated in I the Catawba Technical Specification 6.2.3. 13.4.3 AUDIT PROGRAM Operational quality assurance actisities are periodically audited by the Quality Assurance Departme nt. A detailed description of this audit program is contained in Topical Report, DUKE-1A. The Nuclear Safety Resiew Board is also responsible for audits of certain operating activities as discussed in Section 13.4.2, " Independent Review" on page 13-23. 13.4.4 -OPERATING EXPERIENCE PROGRAM The purpose of the Operating Experience Program (OEP) is to confum nuclear safety and to optimize reliability through systematic evaluation of events occurring at Duke Power Company nuclear units, as I well as at other facihties. The results of this evaluation are then used to identify procedural and/or design changes which may mitigate or preclude the recurrence of a similar event or transient. In order to assure
. that the program is truly effective,'information gained from Duke Power Company experience is disseminated to other organizations, as appropriate.
In order to achieve the objectives of the OEP in an efficient manner, an oft-site organization has been established. as well as an on site organization at each of the nuclear stations.
. The on site organization includes the Station Alanager, who is responsible for the operation and safety of the plant; the Nuclear Station Safety Review Group (SRG), which prepares reports on events and reviews the adequacy of corrective ac* ions; and the supervisors of areas relevant to an event, who may perform the initial investigation and must implement corrective actions.
The off-site organization _ consists of principal engineering support groups, who interface with station personnel and other orgamzations in investigating events and developing remedial actions; company management, who holds overall responsibility for nuclear plant safety; and the Nuclear Safety Review Board (NSRB) which performs an independent review function. l l L REY:(DRAIT NOV 1991) 13-25
l 3,.- -.- .'- '* 13.5 Station Procedures - Catawba Nuclear Station 1 13.5- STATION PROCEDURES 13.5.1 ADMINISTRATIVE PROCEDURES 13.5.1.1. Conformance With Regulatory Guides Regulatory Guide 1.33, Revision 2, " Quality Assurance Program Requirements," and ANSI N18.71976,
" Standard for Administrative Controls for Nuclear Power Plants", is being used for the preparation of administrative and plant procedures.
13.5.1.2 Preparation of Procedures For opnating, emergency, maintenance, instrument, periodic test, chemistry, radioactive waste management, _ health physics, emergency preparedness, annunciator responses, and modification procedures, each procedure is assigned to a member of the station staff for development. Initial procedure
~
1 drafts are reviewed by members of the station staff; the Nuclear Generation Department General Office, 1 - and other departments within Duke; and by personnel from the NSSS supplier and other vendors; as
. appropriate. Following resolution of review comments, if any, a revised procedure is prepared and
- forwarded to a previously designated qualified reviewer for review and comment. This qualified resiewer also~makes the determination whether or not any additional, cross-disciplinary review is required.- ~ After all required and appropriate reviews have been completed a final version of a procedure is prepared.
_1 _ Upon approval by the responsible implementing manager, a procedure becomes available for use.
~l Additional discussion of procedure preparation control is contained in Topical Report, DUKE I A, Quality Assurance Program and in the Technical Specifications.
' All procedures are prepared by qualified personnel, reviewed as necessary and approved by the station Stanager or his designee prior to use.
- 13.5.1.3 Administrative Procedures -
Station administrative procedures (Station Directives) and Alaintenance hianagement Procedures are written as necessary to control station testing, maintenance, and operating activities. Listed below are several areas for which administrative procedures are written, including principle features:
- 1. The reactor operator's authority and responsibility: The reactor operator .is given the authority-to manipulate conttols which directly or indirectly affect core reactivity, including a reactor trip if he deems necessary, Ile is also assigned the responsibility for knowing the limits and setpoints associated with safety related equipment and systems as specified in the Technical Specifications and designated in the operating procedures.
- 2. The senior reactor operator's authority and responsibility:_ The senior reactor operator, in addition to the authorities and responsibilities described for the reactor operator, is given the authority to direct the licensed activities of the reactor operator and ultimately is held responsible for all licensed activities at the station within his control.
- 3. Activities affecting station operation or operating indications: All station personnel performing functions which may ailect unit operation or control room indications are required to notify the Control Operator (licensed reactor operator) prior to initiating such action. Removal of an instrument or component from service requires the pennission of the Shift Supervisor or Assistant Shift Supenisor (licensed senior reactor operetors).
' REY: (DRAIT NOV 1991) 13-26
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' 13.5 Station Procedures Catawba Nuclear Station
- 4. Manipulation of facility controls: No one is permitted to manipulate the facility controls who is not a licensed reactor operator or senior reactor operator, except for license train.cs operating under the direction of a licensed operator. The licensed operators are required to comply with the requalification program as described in Section 13.2, " Training" en page 13-15.
- 5. Responsibility for licensed activities: Responsibility for directing the licensed actisities of licensed operators is assigned to indisiduals with senior reactor operator licenses by virtue of their position within the station organization. !
6 Relief of Duties: This procedure provides a detailed checklist of applicable items for shift tumover.
- 7. Equipment control: Equipment control is maintained and docomented through the use of tags, labels, stamps, status logs or other suitabic means.
- 8. Master surveillance testing schedule: Thts procedure establishes a master surveillance testing schedule to assure that required testing is performed and evaluated on a timely basis. Suncillance testing is scheduled such that the safety of the station is not dependent on the performance of a structure, system or component which has nm been tested within its specified testing interval. The master surveillance testing schedule identifies surveillance and testing requirements, applicable procedures, and required test frequency. Assignment of responsibility for these requirements is also indicated.
- 9. The following log books are maintained and reviewed by appropriate personnel:
- a. Reactor Operations Logbook - This document contains significant events during each shift such as reactivity changes, alanns received, abnormal conditions of operation due to auxiliary equipment and all releases of radioactive waste,
- b. Shift Supervisor Imgbook This document contains a summary of unit operation for each shift, explaining significant events in greater detail than would be expected in the Reactor Operations L.ogbook.
- 10. Temponuy Procedures: The use of temporary procedures is dhcussed in Section 13.5.2.1.3,
" Temporary Operating Procedures" on page 13-29
- 11. Fire Protection Procedures: Fire protection procedures are written to address such topics as training of the fire brigade, reporting of fires, and cont-ol of fire stops. The station's administrative senices group has responsibility for fire protection procedures in general, with the station's maintenance section having responsibility for certain fire protection procedures such as control of repairs to station fire stops.
A Station Directive is written which requires a reactor operator or senior reactor operator to be present at the controls at all times during the operation of the facility. The area designated "at the controls" is defined by Figare 13-6 on page 13-33.
- Adminative w special orders of a transient or self canceling nature are issued (and rescinded if necessary) t>y the use of intrastation memoranda.
The administrative control of maintenance is maintained as follows:
- 1. In order to assure safe, reliable, and efficient operation. a comprehensive maintenance program for the station's safety-related structures, systems and components is established.
1 2. The Mechanical Superintendent is responsible for directing the performance of station maintenance
- 1. activ; les alTecting mechanical equipment. The I&E Superintendent is responsible for directing the I performance of station maintenance activities affecting instrumentation and electrical equipment.
- 3. Personnel performing maintenance activitics are qualified in accordance with applicable codes and standards, as appmpriate.
REY:(DRAIT NOV 1991) 13 27
[ Q. 4 ' ,13.5 Station'Proentures Catawba Nuclear Station
'4 Maintenance is performed in accordance with written procedures which confonn to applicable codes, !
standards, specifications, criteria, etc.
- 5. Maintec.ance is scheduled so as not to jeopardize station operation-or the safety of a reactor or Te Mtors.
- 6. Maintenance histories are maintained on station safety-related structures, systems and components.
l 1 . He admmistrative control of modifications is discussed in Topical Report, DUKE 1 A, Quality Assurance l Program.
-l 13.5.2 . OPERATING AND MAINTENANCE PROCEDURES
-13.5.2.1 Operating Procedures 13.5.2,1.1- System Procedures Operating activities which afTect the proper functioning of the : station's safety-related systems and i components are performed in accordance with approved, written procedures. These procedures are intended to provide a pre planned method of conducting operations of systems, in order to eliminate errors due to on the-spot analyses and judgements.
Operating procedures are sufliciently detailed that qualified individuals can perform the required functions without direct supervision. Written procedures, however, cannot address all contingencies and operating
-procedures, therefore, contain' a degree of flexibility' appropriate to the activities for which each is applicable.-
L Typical activities addressed by operating procedures are: Auxiliary Building Ventilation System Operation Auxiliary Feedwater System Operation Boron Recycle System Operation themical and Volume Control System Operation
- Component Cooling Water System Operation
' Condensate and Feedwater Systems Operation Condenser Circulating Water System. Operation Containment Ventihtion System Operation Containment Spray System Operation ~ -
; Control Building Ventilation System Operation
- Degasification of the R? actor Coolant System -
- Demineralizer Resin Removal and Replacement Electrical Systems Operation Emergency Diesel Generator Operation Failed Fuel Detection and llandling
= Fi! Sng and Draining of the Refueling Canal Filling, Ven:ing and Draining of the Reactor Cochmt System Fire Protection Systems Operation Instrument Air System Operation -
Nitrogen System Operation Nuclear Fuel Control And Accountability Nuclear Service Water System Operation Oxygen System Operation REY:(DRMT NOV 1991)- 13-28
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~y ll3.5 ~ Station Procedures Catanba Nuclear Station -
13.5.2.1.4_ Arnunciator Response Procedures
- Annunciator response procedures are written which specify operator actions necessary to respond to an off normal condition as indicated by an alarm. The fonnet fot annunciator response procedures includes akrm setpoints, probable causes, automatic actions, immediate manual actions, supplementary actions, and applicable references.' ;l
'In order to insure that annunciator response procedures are readily accessible for reference, a positive - ,
method is employed to allow their retrieval. Each annunciator panel is designated by a unique and . obvious nameplate. All of the annunciator windows within a panel are designated by identifying names, The annunciator response procedures are grouped by panels, then subdivided by annunciator names so that the response procedure for any annunciator may be quicidy located. 13.5.2.2 ' other Procedures 13,5.2.9.1, Maintenance Procedures Maintenance of station safety related structures, systems and components is performed in accordance with written' procedures, documented instructions, or drawings appropriate to the circumstances (for example, skills normally possessed ' by '. qualified maintenance personnel may not require detailed step-by step delineation in a _ written procedure) which conform to applicable codes, standards, specifications, criteria,
- etc._ _Where appropriate sections of related vendor manuals, instructions or approved drawings with
- acceptable toicrances do not provide adequate guidance to assure the required quality of work, an
-approved, written maintenance procedure is provided.
' Each procedure is sufficiently detailed'that qualified workers can perform the required functions without
- direct: supervision. Written procedures, however, cannot address all contineencies and maintenance
_ procedures, therefore, contain a degree of= flexibility appropriate to the activities for which each is applicable, 1 The-Mechanical Superintendent has responsibility' preparation and implementation of. maintenance' ' procedures - 13.5.2.2.2 Instrument Procedures
. Maintenance, testing, and calibration of station safety related instruments is performed in accordance with -
written, approved procedures. J Each procedure is sufliciently detailed that liualified workers can perfonn the required functions without ~
-direct supervision.. Written procedures, however, cannot address all contingencies and therefore contain a -
, degree of flexibility appropriate to the activities for which each is applicable.
1 The I&E Superintendent has responsibility for preparation and implementation ofinstrument procedures. 13.5.2.2.3 Periodic Test Procedures Testing conducted on a periodic basis to deterndne various station parameters and to verify the continuing - g capability of safety-related structures, systems and components to meet performance requirements is conducted in accordance with approved, written procedures. Periodic test procedures are utilized to perform such testing and are sufliciently detailed that qualified personnel can perfonn the required functions without direct supervision. 7 g REY:(DRAIT NOV 1991)_ 13-30 J y - w eem, c , n -
., .- - . . - ~ - . - -- -- . -. -.- - -- - - - -
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--f *P 13.5 Station Procedures Catawha Nuclear Station 1 Periodic test procedures are performed by the station's Chemistry, Radiation Protection, Operations, .
1 - Mechanical, and 1&E groups. 13.5.2.2.4 Chemistry Procedures-- L Chemical and radiochemical activities associated with station safety-related structures systems, and components are performed in accordance with approved, written procedures and the station chemistry. manual. Each procedure is sufficiently detailed that qualified workers can perform the required func. is without l direct supervision.- Written procedures, however, cannot address all contingencies and therefore contain a degree of flexibility appropriate to tl'e activities for which each is applicable.
-The station's chemistry 'section has responsibility- for preparation and implementation of chemistry
- procedures.
. 13.5.2.2.5 Radioactive Waste Management Procedures Radioactive waste management activities associated with the station's liquid,' gaseous, and solid waste systems are performed in accordance with appioved, written procedures.
Each procedure is suflici:ntly detailed that qualified workers can perform the required functions without direct supervision. Written procedures, however, cannot address all contingencies and therefore contain a degree of flexibility appropriate to the activities for which each is applicable. The ; station's operations group and chemistry .and health physics sections- have responsibility for ' , preparation and implementation of the radioactive waste management procedures.
;I: -13.5.2.2.6 Radiation Protection lInformation concerning these procedures is presented in Section 12.5.3, " Procedures" on page 12135.
13.5.2.2.7 Plant Security Procedures nfo1mation conceming these procedures is presented in the Station Security Plan. l3.S.2.2.8 Emerger;y Preparedness Procedures
- Information conceming ethese procedures is presented in _ Section 13.3, " Emergency ' Planning" on -
page.13 22. 13..".2.2.'S Material Control Procedures
.information concerning thue procedures is presented in Duke Power Company Topical Report, Quality
= 1- Assurance Program, DUKE-IA. 13.5.2.2.10 Modification Procedures Information concerning these procedures is presented in Duke Power Company Topical Report, Quality 1 ~ Assurance Program, DUKE-1A. REY: (DRAIT NOV 1991) 13-31
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