ML20097D326

Affidavit of DE Deviney Re ASLB Questions Concerning Completion of Qa/Qc Procedures

ML20097D326
Person / Time
Site:	Comanche Peak
Issue date:	09/13/1984
From:	Deviney D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20097D278	List: ML20097D274 ML20097D309 ML20097D326 ML20097D332
References
OL, NUDOCS 8409170443
Download: ML20097D326 (6)

Text

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Attachment 2 UNITED STATES 07 AMERI(A 0%ME,T,ED NUCLEAR REGULATORY C0:0!I!SION 3E70RE THE ATOMIC SAFETY AND LICE'.3INC E0ARD '84 EP M P3 'i In :he Mc:ter of )

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TEUS UTII.ITIES EI.ECTRIC ) Decket Nos. 50- h5 and COMPANY el aJ1,. ) 50-l.46

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(Co=anche Peak Steam Electric ) (Applica:icn fer Station. Units l 'and 2) ) Operating Licenses).

AFFIDAVIT OF DAVID E. DEVINEY CONCERNING BOARD QUESTIONS REGARDINC COMPLETION OF OA/0C PROCEDURES My name is David E. Deviney. My busin2ss address is Comancha Paak 1:sa:  ;

Elastric Station. P.O. 3ox 1300. Glen Rose. To::ss 76043. I a: :Fe opera:1:ns qua:,1:y assuranca Supstvisor.for the ensi:e quality assurance sec: ten at C ancha Peah 3:at:

Electric Station ("C75ES"). In that capacity I am responsible for quali::* centrol inspection, quality surasillance, and procedure review for operations. :n additten.

I c= the quality assurance representative on the ita:Lon Opera:icas Reviav Cc si::es.

A s:stenant of er educational and professional qualifica:icna is atta:hai :: this affidevic (A::ach=an: A).

The purpose of this Affiday:: is te respond :o ths *1carsing I:sid's request for evidence "that appropriate QA/QC procedures hr.ve been conpisted fer ::,7. phart.: of the netivities for which a license is sought...." *. icansing Board's "Manorander' (Kaquert for Evider.ce Relevant to 7ual Leading)" (August 24 1984) at p.2.

i In resw ase :o the 3 card's request, a review of the ::stus of :he precedures :s l

be used for the requested activities uns conducted. This review indica:es that all such procedures have bean ;repared, revisved anf are either appr:ved er in tha pr: cess of Saing approval. All vill be a;pr:vad and av:11ah,a for 'us art:r : f u t '.

l load. The basic preceduras to be used for thast activi:ies are :he M ini:is!  !

star:up procedures (" 5U"> for fual, Icading 1:4 precritical testing listad 1.

Attachment 3. All but two of these procedures have reccived f_nal approval. These two procedures, ISU-008A, Ther:a1 Expansion, and ISU-009A, Si=ulated Red Centrol System Test, have been prepared and are undergoing final review. They must be approved before fuel lead. ISU precedures cddress spacific plant ac:ivi:ies (e.r.,

fuel leading) and detail in step-by-step fashion all ac:icns and pesition assignnents necessary to complete the activity in cuestion. These precedures include appropria:e hold peints to provide independent verificction by QA of critical data such as thc:

used for test. acceptance.

ISU procedures are prepared by test engineers in coordina:icn with operations and QA persennel. Prior :o acceptance, these precedures cre indeperdently reviered by the Station Operations' Review.Co==ittee, which includes C.uali:y Assurance represey.:acion. In addition, each ISU precedure is reviawed by :he TEC 5:aff, cnd those ISU procedures involving the nuclear steam supply syste= are also reviewa[ by cogni: ant Westinghouse personnel.

Other routine plant precedures which cay be referenced in or provide supper: isr-the ISU precedures and associated activities include Syste C;erc:icn Pr:cedures, Nuclear Engineering Precedures and Maintenance and Surveillance Precedures. These procedures have also undergene a ricereus review :nd approval cycle and are currently av ilable fer implemen:ation. .Also, appropriate Technical Specific::icn requiremen:s cust be r et for applicable plant opera:1cnal code.

While the ISU. procedures form the core of procedures :e be used during fuel loading and precritical testing activities, other coordinating /oversign: prec:dures include QC inspection, QA surveillance and QA audit precedures which provide independen and additienal'assurcnce that plant activities, including those related direc:ly :s fuel. loading and precri:ic:1 :es:ing, are properly condue:ad and documented. These addi:1cnal ecordinating/oversigh: procedures have also been

--.co=pleted, rev swed, appreved and are curren:1y in service.

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• In conclusion, based on a complete and thorough review, virtually all QA/QC procedures relating to fuel load and precritical testing are currently available for use. The remaining few are currently in the approval cycle and will be available in time to support fuel load and precritical testing activities.

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David E. Deviney ]

l County of Somervell )

) ss:

State of Texas )

Subscribed and sworn to before me this 13 day of September, 1984.

NotaryPubye Commission expires: 09/04/85 -

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. ,.u. . n..e6 A D A'.*ID E. DEt.*INEY STATEMENT OF EDUCATIONAL AFD PROFESSIONAL QUALIFICATIONS POSITICN: Cperations cuality Assurance Supervisor FOP 2AL EDUCATION: 1967-1968 Texarkana Junior College 43 Semester Hours - Major: Ma:he=a:ics 1968-1970 University cf Tenas at Arling:cn

'35 Se= ester Ecurs - Major: Mathematics 1970-1971 U.S. Navy Electrician's Mata A School 1971-1972 U.S. Navy Nuclear Power School 1977-1979 Tarrant Ccunty Junior College 54 Seces:er Heurs - Major: Electrenics Degree: AAS Electronic's Technology (?cver) 1980-1981 Tarleten State Universi:y 21 Secester Ecurs - Major: Susiness CERTIFICATION: Quality Engineer by A=erican Society for Quality Centrol EXFERIENCE:

1530 - Present Tenas Utilities Generatinz Co=oany Title -- Opera:1cns Quality Assurance Superviser. ?.aspensible for develo: cent and i=o.lecentatien of a cuali:v. Assur,- ce Surveillance Progra :nd 0.uali:"J Centrol Irsrec:icn Pre rac b to meet ce=pany and regulatory requirements for a ec=nercial nuclear power plant. This also includes reviewing and approving purchase requisi:icns and representing the ec=pany in matters invciring quality assurance.

1979 - 1980 Tenas U:ilities Generatine Cc=canv Title - Senior Technician,' Maintenance. ITork included develeping a quality centrol progrc= for the' Maintenance Department, procurecen:

of spare parts, developing a calibratien program and technical suppott for all phases of maintenance.

-1976'- 1979 Tenas U:111:ies Generatine Ceccanv Title - Technician, cuality Assurance. Ucrk included reviewing all nuclear safety-related electrical and protective Oca:in: procedures and ins:ructicns for construe:1cn cf Cccanche Peak F: ace Elec:ric Statica.(a nuclear pover generatin5s:ation) ane "::: bleshco in;"

cuality proble=s in these areas of inspec:icn. Also perferred surveillances in all areas of construction :o verify ccepliance vi:h established recuirements. Instru= ental in developing a Cuality Assurance Program fer C?SES. Du:1es also included vender audies, rele2se inspec icns and cuali:y central inspec:1:n for en-s :e _

=achine shep.

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D'?ER!ENCE - centd.

1970 - 1979 U.S. Navv Electrician's Mate, First Class, with U.S. Navy on USS Grayling, a nuclear povered fast attach submarine. Key duties inclufed raintenance and rep:ir of all sut=:rine electrical ecuiptent, various vacchstanding respcnsibilities en nuclear recctor and systers, planning.and supervising scuba diving operaticns, maintenance and repair of onygen analycer and =aintenance and updating of technical canuals. Also duties included training cf ncv perscnnel in all of

-the above.

1969 - 1970 Reboenition Ecuirment, Inc.

Work included inprocess and final inspection of precision =achined parts for high speed data processing equipment. This required use of precision inspection equipment working to close tolerances.

1969 - 1969 Clarke-Aiken Coreany Work included inprocess and final inspection of machined parts for the aircraft industry. This required use of v:ricus inspection equipment nor ally fcund in the machine shop.

1968 - 1959 Recognition Ecuiceent. Inc.

Work included inprecess and final inspection of precision machined parts _for high speed data processing equipment. This required use of precision inspection equipment verking to close tolerances.

1956,- 1968 Lene Star Ar=v A==unitten Plant Work included receiving inspection, inprecess inspection, final inspection, and packaging and shipping inspecti:n of parts, components, and high enplosives. This required use of varicus.

inspection and test equiptent.

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. ATTACEMENT 9 INITIAL.STARTUP PROCEDURES TO BE CONDUCTED DURING FUEL LOAD AND PRECRITICAL TESTING Procedure Nc. Title ISU-001A Initial Fuel Load Sequence ISU-003A Core Loading Instru=ents:icn and Neutren Source Checks ISU-006A RCS and Secondary Coolan: Chemistry ISU-008A Thermal Expansion ISU-009A Simulated Rod Control Systen Test ISU-010A. Post Core Lead Precritical Tes: Sequence ISU-012A Control Rod Drive Operability Tes:s ISU-013A Rod Drop Ti=e Measurement

-ISU-014A Rod Position Indication Tests

.ISU-015A Reactor Trip System Tests ISU-016A Incore Moveable Detec:cr Sys:c Ali;ntent a

ISU-020A Startup Adjust =ents of the Res:::: Control Syste=

ISU-021A Pressuricer Spray and Heater Capability

'ISU-022A- Reac:oi Coolan Syste -Leakage Rate Tes:

ISU-023A 'Reac:c Coolan: Flow Measurement ISU-024A Reactor Caclant Syste= Flev Coas:devh Tests ISU-025A- RCCA Centrol System Test

ISU-206A Auniliary Feedvater. Performance ISU-211A Lo'ose Parts Menitoring 3aseline Ds:a

-ISU-221A- Inverse Coun: Ea:e Rc:ic Monitering ISU-234A Main-Stea: Isolation Valves Operability and Respense Times