Text

Proposed Changes to Tech Specs Chapter 6 Re Administrative Controls.Resumes for DA Nauman,Kw Nettles,Dr Moore & Os Bradham Encl
	ML20077D675
Person / Time
Site:	Summer
Issue date:	07/22/1983
From:	; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML20077D669	List: ML20077D666; ML20077D675;
References
	NUDOCS 8307270013
	Download: ML20077D675 (28)
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6.0 ADMINISTRATIVE CONTROLS

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6.1 RESPONSIBILITY parseror dasle=* Plur O erro*~e t

6.1.1 The M;r.;;;r,, '!'rgil 0. T - : " :1:;r St ti:r shall be responsible for overall unit operation and shall delegate in writing the succession to thte responsib

t. o. titii,lity mdu. FI.~r 0 d r ** d3 e.,ring his absency.cie.e rhe title P.<e r r, A.te.

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6.1.2 The Shift Supervisor shall be responsible for unit operations. A management directive to this effect, signed by the Vice President, Nuclear Operations, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION k'

0FFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2-2 and:

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 Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one Licensed Senior Reactor Operator shall be in the Control Room.

c. A health physics technician # shall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

e. A site Fire 8pigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Supervisor and the other 2 members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

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The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

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SUMMER - UNIT 1 6-1 8307270013 830722 PDR ADOCK 05000395 P PDR

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> 1 ADMINISTRATIVE CONTROLS

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f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions; e.g. ,

senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

( Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

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a. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

( straight, excluding shift turnover time.

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b. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between work periods, including shift turnover time.

d. Except during extended shutdown periods, the use of overtime should be -

considered shift. on an individual basis and not for the entire staff on a 1

o yA.__J,py,,igi,9Ajpggghg,gbogg,puidelines shall be authorized by the m , vi,9.. u. oummer nuuicoi

. .acr. or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedure ua reviewed monthly by the %gerg h,rg )r ._v,1_ av > gog M $ime shallm, ar- Stat bc or his ,

designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized. '

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SUMMER - UNIT 1 6-la

TABLE 6.2-1

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MINIMUM SHIFT CREW COMPOSITION

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SUMMER UNIT 1 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3, & 4 MODES 5 & 6 k 1 1 SS[

CR 1 None R0 2 1 A0 2 1 -

STA 1 None (

SS 4 -

Shift Supervisor with a Senior Reactor Operators License on Unit 1 CRF - Control Room f6NIMwith a Senior Reactor Operators License on Unit 1 R0 -

Individual with a Reactor Operators License on Unit 1 A0 -

Auxiliary Operator STA - Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift 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.

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s ecevw During any absence of the Control Room Feremen from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SR0 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 RO or SR0 license shall be designated to assume the Control Room command function.

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( 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information, including plants of

( similar design, which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of a multi-disciplined dedicated onsite group l

with a minimum assigned complement of five engineers or appropriate specialists.

j RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant i activities to provide independent verification

that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for procedure revisions, equipment modifications, maintenance activities, operations activities or other ;

means of improving plant safety to the Group Manager, icic = Engin :H ng end-Linnr i ,- Taskuical Jeevices. 1 6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant i analysis with regard to the safe operation of the unit.

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum !

qualifications of ANSI N18.1-1971 for comparable positions and the supplemental l requirementsspecifiedinSectionsAgg,qfgpiq,sure1oftheMarch letter to all licensees, except for the ..r :t. Nealth Physics who shall28,meet 1980 ,

j or exceed the qualifications of Regulatory Guide 1.8, September 1975, the Shift Technical Advisor who shall meet or exceed the qualifications referred to in Sec-tion 2.2.1.b of Enclosure I of the October 30, 1979 NRC letter to all operating nuc' ear power plants, and the members of the Independent Safety Engineering Group, eacn of whom shall have a Bachelor of Science degree or registered Professional Engineer and at least two years experience in their field. At least one year experience shall be in the nuclear field.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommentiations of Section 4.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the s 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 , identified relevant industry operational experience.

"Not responsible for sign-off function.

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PRESIDENT AND CHIEF OPERATING OFFICER EXECUT IVE VICE PRESIDENT OPERATIONS SENIOR VICE PRESIDENT ,

POWER OPERATIONS VICE PRESIDENT NUCLEAR OPERATIONS I i NtELEAR NLEL. EAR SERVICES PLANT OPERATIONS I I QUALI TY REGtEATORY AND TECHNICAL NtfLEAR EDUCATION SERVICES SUPPORT SERVICES SERVICES AND TRAINING F IGURE 6.2.1 SOUTH CAROLINA ELECTRIC AW GAS COWANY VIRGIL C. SIN'4ER NUO. EAR STATION OFFSITE ORGANIZATION

DIRECTOR, NLELEAR PLANT OPERATIONS ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~l l

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REGLP.ATORY TECHNICAL AND OPERATIONS AND COMPtIANCE SUPPORT SERVICES l MAINTENANCE l

(~SE[t5EI{Y}

l l l OPERATIONS MAINTENANCE TECHNICAL StPPORT SLPPORT SERVICES l SRO SERVICES I I SHIFT StPERVISORS KCHANICAL CHDtISTRY HEAL TH PHYSICS __j SRO PERSONEL See Note j CONTROL ROOM ELECTRICAL PERFORMANCE ADMINI$TR ATION StPERVISORS PERSONNEt i SRO REACTOR INSTRUMENT AND OPERATORS CONTROL PERSONEL RO FIGlRE 6.2-2 VIRGIL C. StHMER NU(1 EAR STATION fUNCT10NAL ORGANIZATION SRO - Senior Reactor Operator License RO - Rractor Operator License NOTE: Health Physics supervision has direct access to the Director, Nuclear Plant Operations in matters concerning any phase of radiological protection.

NOTE: The title Director, Nuclear Plant Operations is synonymous with the title Manager, Virgil C. Summer Nuclear Station, Station Manager or Plant Manager.

ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)

FUNCTION p,rearor, Nasta e Plaar C>eru.n 6.5.1.1 The PSRC shall function to advise the ".;n;;;r, Virgil C. Su;;;r "u:'^ r St;tica on all matters related to nuclear safety.

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COMPOSITION 6.5.1.2 The Plant Safety Review Committee shall be composed of the:

0,ra ra a r A a e Pisuropren a er Dsp.,ry hamper, Chairman: ltn;;;,r er 0;puty itn;gr, o,.wr-e -s%rew Virgil C. Ca.;T.;r Nu;l;r Stati:r Assi;t;nt Manager Operations k Member:

Member: Assi:;t;nt Manager Technical Support Member: nt Manag a,[r}teggnce Services Member: Ag;pgM,ap3ger,a g;j upport Services Member: a rc t;r o. He,alth Physics or a Health Physics Supervisor ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, no more than two alternates including the Chairman's alternate, if applicable, shall participate as voting members in PSRC activities at any one time.

MEETING FREQUENCY ,

6.5.1.4 The PSRC shall meet at least once per calendar month and as convened [ ,

by the PSRC Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the PSRC necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Safety Review Committee shall review:

a. Station administrative procedures and changes thereto,

b. The safety evaluations for 1) procedures, 2) changes to procedures, (

equipment or systems, and 3) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question and all programs required' by Specification 6.8 and changes thereto.

c. Proposed procedures and changes to procedures, equipment or systems (\

which may involve an unreviewed safety question as defined in j

Section 50.59, 10 CFR.

l d. Proposed tests or experiments which may involve an unreviewed safety l question as defined in Section 50.59, 10 CFR.

! e. Proposed changes to Technical Specifications or the Operating License.

SUMMER - UNIT 1 6-6

ADMINISTRATIVE CONTROLS

f. Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.

g. Reports of significant operating abnormalities or deviations from normal

[ and expected performance of plant equipment that affect nuclear safety.

h. All written reports concerning events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission.

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All recognized indications of an unanticipated deficiency in some aspect of design or operation of s.afety related structures, systems,

( or components.

j. The plant Security Plan and changes thereto.

k. The Emergency Plan and changes thereto. ;

1. Items which may constitute a potential nuclear safety hazard as ,

identified during review of facility operations.

m. Investigations or analyses of special subjects as requested by the !

Chairman of the Nuclear Safety Review Committee. I

n. The unexpected offsite release of radioactive material and the f report as described in 6.9.1.13(e). i

o. Changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION '

MANUAL.

AUTHORITY 6.5.1.7 The plant Safety Review Committee shall:

p,e..ree p oete. < f % r ete r roe-s

a. Recommend in writing to the Man;ger,'!;ig;l C. Sur;,;r M :le:- St; tic-approval or disapproval of items considered under 6.5.1.6a, c, d, e, j, and k above.

p,re aroe r

b. Render determinations in writing to the emnose,, Nocle. Mer e <<<rr;,ssV; w;l C. E r:-

Station with regard to whether or not each item considered under 6.5.1.6a, c, and d above constitutes an unreviewed safety question.

c.

vorearee,goaa.e h -rq.v.rses .

Make recommendations in writing to the Statier 9:n;;u that actions reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question.

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d. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the C;ncral M; ;3s.

Nuclear Operations and the Nuclear SafgR igo,mnggee disagreement between the PSRC r pf i ; lear St; tion however, the p ,,tyg mom

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gpe g,,eg, rgy 4,,g;;g ,,,,,

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Stetierrshall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS l 6.5.1.8 The Plant Safety Review Committee shall maintain written minutes of l each PSRC meeting that, at a mirimum, document the results of all PSRC activ-ities performed technical under the specifications. respc..sibility Copies shall and authoritytoprovigops be provided the Cc.;r:p,}m,)pjpe Or-l l

Nuclear Operations and the Chairman of the Nuclear Safety Review Committee.

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6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)

FUNCTION 6.5.2.1 The Nuclear Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of: '

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering ,

h. quality assurance practices COMPOSITION 6.5.2.2 NSRC shall consist of a Chaiymagg nd four or more other members appointed by the Cr i r Vice Presiden33 ewer d Operations. No more than a minority of the members of the NSRC shall have line responsibility for the operation of the unit.

The NSRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h. In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.

ALTERNATES 6.5.2.3 All al g'rnate members shall be appointed in writing by the 6eneer

_Vice Presidentg " Operations; however, no more than two alternates shall

- -participate as voting members in NSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert advice to the NSRC.

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SUMMER - UNIT 1 6-8

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ADMINISTRATIVE CONTROLS

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AUDITS 6.5.2.8 The NSRC shall have cognizance of the audits listed below. Audits may be performed by using established SCE&G groups such as the ISEG and QA or by outside groups as determined by the NSRC. Audit reports or summaries will be e the basis for NSRC action:

a. The conformance of unit operation to provisions contained within the

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Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire unit staff at least once per 12 months. b

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. Tne Emergency Plan and imole-enting procecures at least once per L2 months. g ,

f.

The Security Plan and' implementing procecures at least once per 12 months.

g.

Any other area of unit operati n go,nsidered appropriate by the NSRC (7 or the Semer Vice President, Operations.

h. The Fire Protection Program and implementing procedures at least once per 24 months.

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An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or a qualified outside firm.

J. An inspection and audit of the fire protection. and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

k. The radiological environmental monitoring program and the results thereof, including the performance of ac'tivities required by the ('

quality assurance program per R.G. 4.15 Rev. 1, February 1979, at least once per 12 months.

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for '

solidification of radioactive wastes at least once per 24 months.

AUTHORITY A 6, 6.5.2.9 The NSRC shall report to and advise the Semw Vice President, Pewer Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8. (

SUMMER - UNIT 1 6-10 Amendment No. 9

i ADMINISTRATIVE CONTROLS f RECORDS 6.5.2.10 Records of NSRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSRC meeting sy g be prepared, approved and forwarded

(' to the Semer Vice President, Fewer Operations within 14 cays following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the See++c Vice President,Dewer#ve.Ine-Operations within 14 days following completion of the review.

( c. Audit summary reports encompassed by Section 6.5.2.8 aboge J all be forwarded to the NSRC and to the See4ec Vice President, Roues Opera-tions. Full audits shall be forwarded to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Procedures required by Technical Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual /

group which prepared the procedure or procedure change. Procedures a

other than Admi in writing by t ei,gr g py a rr m rAc

r.- g g ,The wjll St

t;: r be g y._n:; p g rsJel,i.ng$

w1M ap rove g, administrative procedures, security implementing procedures and emergency plan implementing procedures. Temporary approval to procedures which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least ene of whom holds a Senior Reactor Operator's License. For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change.

b. Proposed changes or modifications to plant nuclear safety-related strgager...;ns;;,s, the r4s 4 gtp gomponents shall be reviewd as designated by

r. ach such modification shall be designed as authorized by Nuclear Engineering and shall be reviewed by an i individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications. Implementation of modifications to plant nuclear safety-related structures, systems and components shall be concurred in by the St: tic" hger. Dieurer, tJu d 4 e f i s r oparh SUMMER - UNIT 1 6-11

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ADMINISTRATIVE CONTROLS

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c. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report shall be reviewed by an individual / group other than the individual / group which prepared the proposed test or experiment.

d. Occurrences reportable pursuant to the Technical Specification 6.9 g and violations of Technical Specifications shall be investigated and (

a report prepared which evaluates the occurrence and which provides recomg Such report shall be approved bythe,$u,viiiopsy.o mo 4 e,v g 'pgcyrrence.

no. .. g ancf forwarded to the Chairman of the Nuclear Safety Review Committee.

e. Individuals responsible for reviews performed in accordance with (

6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall be members of the plant staff that meet or exceed the qualification requirements p*,,

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-- S.t,{oj:(nager a cr . 4 Each g gf,,6NJ,1,18.1, 1971,include such review shall as previously designated a determination of by the whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.

f. Each review will include a determination of whether or not an unreviewed safety question is involved.

RECORDS

,p4}f 2 Records of the above activities shall be provided to the ""m"Nwle=*- Ma ~T poe.ar

";..agi , PSRC and/or NSRC as necessary for required reviews.

6.6 REPORTABLE OCCURRENCE ACTION (

6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission g l j iewed by the PSRC and submitted to the NSRC andtheOc.m...),p:,e,rp/-NuclearOperations.

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6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

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The NRC possible andOperations in all casesCenter shall within one be notified hour. by telgpjop The Guic... ... S, p.a;oon as Nuclear Operations and the NSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I b. A Safety Limit Violation Report shall be prepared. The report s' hall l

be reviewed by the PSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation k' upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

c.

TheSafetyLimitV{platg=;f,eportshallbesubmittedtotheCommission, the NSRC and the Geners. grr, Nuclear Operations within 14 days of the violation.

SUMMER - UNIT 1 6-12

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1 NAME: Dan A. Nauman POSITION: Director, Nuclear Services FORMAL EDUCATION: U. S. Coast Guard Academy B.S. Naval Engineering (with honors) - 1963 University of Pittsburgh - Post Graduate study in Metallurgy - 1969 Master of Business Administration Program - 1969-1972 University of South Carolina - Executive Development Program - 1979 4

REGISTRATION: Registered professional engineer in the state of California. - --

' EXPERIENCE:

1976 - Present South Carolina Electric 6 Gas Comnany 1983-Present Director, Nuclear Services - Responsible for the technological support associated with the Company's nuclear facility. Included is managerial supervision of the functions of Nuclear Engineering, Nuclear Safety, Independent Site Engineering Eeview, Nuclear Licensing, Corporate Fealth Physics and Environmental Programs, Nuclear Security, Nuclear Fuel Management, Emergency Planning

, and,yuclear fducation and Training. These responsibilities are discharged through four Group Managers and a staff of managers, engineers and technical specialists providing diverse technical education and experience necessary to manage and provide conprehensive support to the nuclear facility under all operational modes. The management of engineering and technical service consultants including the architect / engineer and reactor system supplier is accomplished in this organization.

1981 - 1983 Group Manager, Nuclear Services - Responsible for all nuclear quality and fuel management services associated with the nuclear facility. Included is the develcpment and managerent of quality assurance, quality control and fuel management systems through the Manager, Ouality Assurance; Manager, Muclear Quality Control and the Manager, Nuclear Fuel Management. Quality activities include the develop-ment and implementation of review, surveillance audit and inspection programs in support of safe and reliable operation of the nuclear plant. Fuel management includes incore and excore activities associated with design and procurement of reload cores and systems associated with spent fuel disposition. Development and management of analytical models necessary to support neutronics calculations

1981 - 1983 (cont.) leading to reload design and safety analysis capability while maintaining operational support of station reactor engineering is a major responsibility. Fuel Management is held accountable to assure that recuired reloads are available when they are needed, configured in a fashion to safely produce maximum energy content utilization at the lovest possible cost.

1978 - 1980 Group Manager of Ouality Assurance and Security - In g addition to the responsibilities indicated for quality assurance below, managed the development of both nuclear and conventional security systems within the Company through the Manager, Ouality Assurance and the Manager, Security. - Developed the organtra-tion to not only operate, but design, install and maintain diverse security systems. The operational programs ranged from those related to nuclear fuel diversion and sabotage with risk to the public; to those concerned with protection of Company personnel and property.

1976 - 1978 Manager of Ouality Assurance - Responsible for all aspects of design, development, implementation, surveillance and audit of quality assurance programs within the Company. Accountable for ensuring that all of nuclear safety related structures, systems and conponents for nuclear power plants are designed,

, fabricated,eerected, tested, and operated according to engineering specifications and regulatory requirements.

1972 - 1976 Gilbert Associates, Inc.

1973 - 1976 Ouality Assurance Program Manager - Responsible for the development and implementation of the quality y assurance system for the design, manufacture and installation of a 2775 MWt nuclear power Feneratic" plant. Included are quality aspects of f specification generation, procurement control, vendor surveillance and design control audits for balance of plant systems, audits of the nuclear steam system supplier and associated vendors.

1972 - 1973 Ouality Assurance Mechanical Engineer - Review and evaluation of specifications, proposals, procure-ment documents and drawings, performance of vendor evaluation surveys and analysis, review and evaluation of nethods of manufacturing., non-dectructive resting and inspection within the quality assurance program. Performance of general design and nuclear steam supply system audits.

~

.s Station with intermittent assignment to Wateree Station. Responsible for:

1. Urquhart Station - Coordination of site installation and engineering activities associated with the removal of mechanical precipitators and ;

the installation of electrostatic precipitators on Units #1, #2, and #3.

2. Wateree Station - Various activities associated with the construction of Units #1 and #2 electrical, mechanical, and civil systems, components, and structures including field supervision, field coordination of construction activities.

ADDITIONAL COURSES:

1/78 Principles and Applications of PERT / CPM 9/79 Project Management for Engineers 9/79 Electrical Protection of Computers and Other Electronic Equipment Exposed to Power and Lightning Surges 7/80 Westinghouse Pressurized Water Reactors l

l 11/80 Advanced Electrical Systems Design 11/80 Analog Controls 11/80 Management of Facility Expenditures in the Electric l Utility Industry l

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Site Manager for V. C. Summer Station Unit #1.

Assigned positions included:

1. The Nuclear Site Management Group Staff electrical engineer responsible for all electrical temporary power facilities, for the review of electrical design packages for V. C. Summer Station Unit #1, and for coordination of the constructor's electrical construction program with other project organizations.

2. The Electrical Manager for the constructor's Project Manager, responsible for all construction electrical activities on-site, including engineering management and field supervision, procedural program development and maintenance, electrical design package review for constructability, and coordination of construction activities with quality control and operations.

Mid 1971-Mid 1973 Electrical Engineer, S. C. Electric & Gas Company / Construction assigned to the Electrical Check-out and Start-up Group. Responsible for the electrical check-out and testing of electrical systems and components and turnover of same to operations after initial startup. Performed these activities at Wateree Station, Unit #2 and A. M. Williams Station.

Mid 1970-Mid 1971 Electrical Engineer, S. C. Electric & Gas Company / Construction assigned to Saluda Hydro Unit

5. Responsible for the management and coordination of the electrical installation for the hydro unit.

Activities included supervision of electrical field personnel, resolution of field electrical installation problems with engineering, and coordination of generator installation and testing with the generator contractor.

1968-Mid 1970 Electrical Engineer, S. C. Electric & Gas Company / Construction primarily assigned to Urquhart ;

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problem resolution, as required. The activities included engineering management of design activities of both the A/E and Nuclear Engineering staff engineers.

did 1978-1979 Electrical Engineer, S. C. Electric & Gas Company / Nuclear Engineering, assigned to the site Resident Engineers office responsible for the site activities of A/E electrical and I&C engineers.

Activities included the resolution of construction and start-up problems. This period also included a temporary assignment of approximately eight months during 1979 as the Project Electrical Engineer for the constructor, responsible for the management of all electrical engineering activities on site and the coordination of those activities with various site organizations.

Mid 1975-Mid 1978 S. C. Electric and Gas Company Quality Control Manager for V. C. Summer Station Unit #1. The responsibilities included the development and maintenance of a quality control program for the civil, electrical, and non-ASME Mechanical construction activities at V. C. Summer Station Unit

1, utilizing both SCE&G Company personnel and subcontract personnel. The activities included quality program development and maintenance, personnel training program development and maintenance, and overall quality control inspection program coordination with site engineering, construction, and operations personnel. Responsibilities also included chairmanship of the site Field Review Board Committee for the periodic evaluation of the effectiveness of site quality activities and programs during construction.

Mid 1973-Mid 1975 Electrical Engineer, S. C. Electric & Gas Company / Construction assigned to the SCE&C Nuclear

I NAME: Kenneth W. Nettles, Sr.

POSITION: Group Manager, Technical Services FORMAL EDUCATION: 1963-67 Clemson University B. S. Degree - Electrical Engineering REGISTRATION: Registered professional engineer in the state of South Carolina (#5222)

EXPERIENCE:

January,1983 - Present Senior Electrical Engineer, S. C. Electric & Gas Company / Production Engineering, assigned to the Vice President, Nuclear Operations staff. Responsibilities incluae various special projects as assigned by the Vice President, Nuclear Operations.

1981-1982 Senior Electrical Engineer, S. C. Electric & Gas Company / Production Engineering, assigned to the Group Manager, Construction and Production Engineering and responsible for V. C. Summer Station Unit #1 pipe analysis activities as required by IEB's 79-14 and 79-02. Responsibilities included the engineering management of all A/E activities and the activities of several contractors, including the NSSS supplier, associated with the pipe analyses, both on-site and off-site. Activities included the planning, scheduling, and coordination of design modifications required by the pipe analyses with the construction and start-up organizations.

1980 Senior Electrical Engineer, S. C. Electric & Gas Company / Nuclear Engineering, responsible for the coordination of all electrical and I&C design activities for V. C. Summer Station Unit #1 including design, procurement, and installation and testing

O 1967 - 1971 Quality Control Engineer and Inspection supervisor Tomsend Corpany Responsible for planning product appraisal techniques for a high production product. Utilized existing and/or developed special inspection techniques and sanpling plans; scheduled and directed an inspection staff and mechanical testing lab to acconr:odate plant loading while r:aintaining quality requirenents; designed special gages or mechanical testing fixtures for specialty product designs; provided customer liaison relative to quality related requirenents or conplaints; and participated on the Material Review Board for in-house discrepancies.

1965 - 1967 Engineering Assistant , _.

Arreo Steel Corocration Responsible for layout and detail for modification and installation of fabricating equipment.

ADDITIOMd., EDUCATION: - Radiography and Conplimentary NDE in the Nuclear Industry - 1973

- Management Techniques for Professional. Personnel -

1973 Elements of Quality Control Engineering - 1972

- Design of Experiments - 1971

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- Applied QC Engineering - 1970 Pre MBA Courses at Penn State University - 1976 to 1977 4

- Nuclear Operations Course for Managers at Westinghouse / Zion Simulator - 1982 i

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1975 - 1976 Quality Assurance Assistant Program Panager Gilbert /Cor cmealth Co"canies Responsible for supporting Quality Assurance Program Manager in directing the total Quality Assurance Program efforts for the design, procurenent, and construction of South Carolina Electric & Gas Conpany's V. C. Su:rer Station, Unit 1, 900 IM. Project responsibility included coordination with client, vendor, and prospective vendor personnel to integrate quality program requirerents; administrating assignments within the Quality Assurance Division; participation in quality surveys, and ISSS audits; and procurement activities from specification preparation through vendor inspection. Also responsible for administering IGSS audit and hardware witness prograns. - -

1974 - 1975 Quality Assurance Engineer Gilbert /Comnonvealth Concanies Responsible for supporting Quality Assurance Prograns including the review and evaluation of specifications, vendor proposals, procurement documents and drawings for adequate quality requirements consistent with applicable codes, regulations, and standards. Responsible for the performance of internal design control audits, vendor audits and vendor surveys.

1971 - 1974 Quality Assurance Engineer Westinahouse- Electro-Mechanical Division Total quality assurance project responsibility for nuclear punps and valves. Responsible for review and evaluation of purchase orders and specifications for quality requirenents. Also prepared quality plans for use in the manufacture of nuclear purps and valves.

Responsible for custoner and vendor liaison when quality requirerents or audits wre involved; and review and rodification of the Quality Program Manual. Also in charge of the division's auditing program 5hich assured conpliance with quality program requirenents.

1979 - 1980 Director, Surveillance Systes (CA)

South _ Carolina Electric & Gas Cornany Responsible for surveillance and audit activities to support the CA Program for the V. C. Sumer Station.

Responsible for verifications that plant management and progr ms conplied with regulatory requirements and that suppliers of equipment and services had sufficient controls to provide product that conplied with purchasing documents.

1978 - 1979 Senior Engineer, Quality Assurance South Carolina Electric & Gas Concany Responsible for supporting the OA Pregram for the V. C. -

Summer Station by performing reviews and evalutions of specifications, vendor proposals and procurement documents for adequate quality requirments consistent with applicable codes, regulations, and standards.

Responsible for performance of internal audits and surveillance and vendor audits and surveys.

1977 - 1978 Quality Assurance Program lhnager Gilbert /Cor onwealth Coreanies Responsible for the developent and technical administration of the Quality Assurance Program for the design, manufacture, construction and installation of Ohio Edison,Corpany's, Erie Nuclear Power Plant, Units 1 and 2,1200 !M each. Scope includes quality assurance measures related to specification generation, procurement control, manufacturing and construction surveillance, manufacturer's and constructor's procedure review, design control audits for balance of plant systa, and auditing of 1;SSS suppliers and associated vendors. Also responsible for assisting client in interpretation of KRC and other applicable quality assurance requirements related to the utility industry.

1976 - 1977 Quality Assurnce Program !4anager Gilbert /Comronwealth Coreanies Responsible for the developent and inplementation of the Quality Assurance System for the design, manufacture and installation of South Carolina Electric & Gas Corpany's V. C. Sumner Station, Unit 1, 900 IGl. Scope included quality assurance neasures related to specification generation, procurerent control, vendor inspection, design control audits for balance of plant systems, audits of the nuclear steam system supplier and associated vendors, and site surveillance and audit during construction. Assisted client in interpretation of NRC and other applicable quality assurance requirements related to the utility industry.

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IW1E: David R. Moore POSITION: Group Manager, Quality Services FORMAL EDUCATION: 1962-1971 - Carnegie Mellon University B. S. Mechanical Engineering PEGISTRATIONS: Registered Professional Engineer (Mechanical) in the

< States of South Carolina and Pennsylvania.

Registered Professional Engineer (Quality) in the State of California Merber Southeastern Electric Exchange Quality Assurance Conmittee.

EKPERIEICE: -

1983 - Present Group Manager, Quality Services South Carolina Electric & Gas Conpany Responsible for developaent and irplementation of Quality Assurance and Quality Control Programs for the V. C. Sunner Station. These Quality functions include review, surveillance, audit, and inspection activities associated with plant operations, maintenance, and modification as well as corporate office activities associated with the plant. Responsibilities include assurance that technical specifications, license conditions and other technical requirements and regulat; ions.are conpJied with by responsible line mariagement via prudent application of the Quality functions and proper apprisal of responsible reanagerent.

1980 - 1983 Manager, Quality Assurance South Carolina Electric & Gas Comany Responsible for develoFcent and irplerientation of the Quality Assurance Program for the V. C. Sunner Station.

Inherent in these responsibilities is to assure plant operations, maintenance, modifications and inspections are performed by line responsible organizations by using quality verification rcethods of review, surveillance, and audit. Responsibilities include identification of problem areas to responsible management for resolution and assuring adequate and timely corrective actions are

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ACCLMEATIVE WORK Ebssil power plant 12 months EXPERIENCE BEFORE

FUEL IDADING: Nuclear experience in non power 84 months plant Nuclear power plant design 24 months Nuclear power plant start-up, 238 months i

testing, operation and main-tenance

'Ibtal credible power plant 29 years, experience 10 months 1

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1961-1967 I&C Technician, and Instrument and Electri-cal Supervisor, CVIR Reactor Plant, Parr, S. C. Responsible for maintenance and testing of instrument and electrical plant equipnent from preop through power operation and R&D test program.

1967-1969 I&C Engineer, Duke Power Conpany for Oconee Nuclear Station. Worked with design engi-neering group in writing, reviewing specifi-cations. Selection of plant instrumentation for primary nuclear plant. (bnducted I&C training program for hot and cold license groups for Oconee personnel.

1969-1973 I&C Engineer, Oconee Nuclear Station.

Responsible for selection, hiring and train-ing of plant staff for I&C Group. Respon-sible for I&C portion of preop, start-up, power ascension te.st program and maintenance of all instrumentation for units 1 and 2.

1973-1974 Technical Support Group Supt, Oconee Nuclear Station. Responsible for zero power physics and power ascension test program, unit 3.

Also accountable for I&C Section, Chemistry Section, Performance Section, and Health Physics Section activities for units 1, 2, and 3.

1974-1978 Supt. of Maintenance, Oconee Nuclear Station. Responsible for all &chanical Maintenance Section, Instrument & Electrical Section, Planning / Scheduling and Material Section activities for Station. 'Ihis consisted of manac,ing six refueling outages in adddition to numerous maintenance outages and normal operational support activities.

1978 mintenance Supervisor, South Carolina Electric and Gas Conpany, V. C. Summer Nuclear Station. Responsible for all

&chanical, Instrument and Control, and Electrical Maintenance activities. Also responsible for the Materials Section of the station.

1978- Station Manager, V. C. Sununer Nuclear Station. Responsible for the plant activi-ties during the finalization of the con-struction phase, startup testing, licensing process, initial fuel load, and power ascension test program. Also responsible for the staffing and organization of the plant for an operational mode.

1 NME: O. S. Bradham POSITION: Director of Plant Operations FDRMAL EDUCATION: 1947 High Schoal, Manning, S. C.

1951 Officer Candidate School, Ebrt Benning, Ga.

1952 Mvanced Infantry Officer Course, Fort Benning, Ga.

1953 Infantry Officer Cormunications Course, Ebrt Benning, Ga.

1960 ICS/ Electrical Engineering Course

'IRAINItG: 1954 E. I. DuPont (SRP) Instrument and Controls Course (Pneurutic) 1955 E. I. DuPont (SRP) Instrument and 03ntrols Course (Electronic) 1961 Foxboro Instrument & Controls Course, Ebxboro, Mass.

1962 Westinghouse Nuclear & Radiation Monitoring Course, East Pittsburgh, Pa.

1968 Duke Power Conpany Second Level Managenent Course, Hickory, N. C.

1969 Babcock & Wilcox PWR Systen Design Course, Lynchburg. Va.

1970 Bailey Meter Conpany Reactor Protective and 721 Analog Control System Courses, Wickliffe Ohio 1977 Dtle Power Conpany Myanced Managenent Training, Hickory, N. C.

EXPERIENCE: 1953- Instrument 'Ibchnician, Savannah River Plant.

1961 Performed calibration and maintenance on reactor plant equipnent.

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ADDITIONAL TRAINING AND EDUCATION: Reliability in Nuclear Power Generating Stations -

IEEE Standards Board - 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months - 1974 Reliability Engineering Conference for the Electric Power Industry - M.E. Department University of Miami - 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months - 1979 Concepts and Applications of Quality Circles -

Trident Technical College - 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months - 1981 Nuclear Operations Course for Managers -

Westinghouse / Zion Simulator - 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months - 1982 Nuclear Plant Systems and Processes for Managers and Engineers - SCE6G Nuclear Training Center -

70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months - 1982 Westinghouse Electric Utility Engineering Conference - 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months - 1983 EPRI Transfer of Technology Conference - ,

Chicago, Illinois - 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months '1983 O 6 f

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1968 - 1972 Westinghouse-Bettis Atonic Power Laboratory, West Mifflin, Pennsylvania 1970 - 1972 Senior Mechanical EnFineer - Performed feasibility study and conceptual design of fueling / refueling '

system for an advance submarine reactor. Proj ect Engineer on the design and procurement of several multi-million dollar items associated with the A-4-W reactor plant. ,

1968 - 1970 Mechanical Enrineer - Design of, and specification preparation for, fueling / refueling systems required for new class aircraft carrier and associated prototype plant installati6'n at Naval Reactors --

Facility, Idaho. Included equipment design and preparation of specifications, system descriptions and servicing operational procedures.

MILITARY SERVICE: Comnissioned Officer, U. S. Coast Guard - 1963-1968 1967 - 1968 Perchant Marine Inspector during all phases of construction and testing of commercial marine vessels. Inspection consisted of general surveillance, radiographic examination of weldments, ultrasonic gaging and examination, P.T. and magnetic particle examination, materials testing and a'certificatien, welder qualification and vessel start-up and operational testing.

1963 -1967 sea Duty Oualified engineering watch officer on steam turbine and diesel propulsion plants. .

Assistant engineering officer and damage control assistant. Oualified deck watch cfficer.

Participated in two majot shipyard overhauls.

I ADDITIONAL TRAINING AND EDUCATION: Damage Control / Nuclear, Biological, Chemical Warfare Schcol - U. S. Coast Guard - 4 month school-1965 Fire Fighting / Emergency Operations School - U. S.

Coast Guard 3 week school - 1965 Merchant Marine Inspection School - U.' S. Coast Guard 6 month course in ship design, construction, testing and inspection - 1967

ML20077D675

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