ML20137F097

Forwards Proposed Changes to FSAR Addressing SER Open Item 11 Re Licensee Qualifications,As Discussed on 850805

ML20137F097
Person / Time
Site:	Vogtle
Issue date:	08/21/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
0053V, 53V, GN-689, NUDOCS 8508260146
Download: ML20137F097 (6)

Text

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Georgia Powtr Company

• Route 2 Box 299A Waynssboro, Georgia 30830 Telephone 404 5544961 404 724-8114 Southern Company Services, Inc.

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 Vogtle Proj.ect August 21, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Ms. Elinor G. Adensam, Chief Log: GN-689 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: Bailey to Denton, GN-647, Dated 6/25/85 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 SER OPEN ITEM 11: LICENSE QUALIFICATIONS

Dear Mr. Denton:

Attached for your staff's' review are proposed changes to the FSAR addressing the SER outstanding item' s as discussed on August 5, 1985. Please note that portions of these changes incorporate changes to the referenced document. It is felt that the referenced document, portions of the referenced document as changed by this attachment, and the additional information contained in this attachmant address all of the outstanding items as listed in the SER.

If your staff requires any additional information, please do not hesitate to contact me.

Sincerely, e

J. A. Bailey Project Licensing Manager JAB /sm Attachment xc: D. O. Foster G. Bockhold, Jr R. A. Thomas T. Johnson (W/o Att.)

J. E. Joiner, Esquire D. C. Teper (W/o Att.)

B. W. Churchill, Esquire L. Fowler M. A. Miller W. C. Ramsey B.. Jones, Esquire (W/o Att.) Vogtle Project File L. T. Gucwa gROB260146 850821 0 0053V E ADOCK 05000424 PDR E M\

VEGP-FSAR-13 Collectively, these members possess the type and degree of expertise required to review unplanned events and proposed changes to systems, procedures, tests, and experiments that affect nuclear safety. The chairman and vice chairman of the PRB are designated by the GMVNO. The minimum quorum of the PRB will consist of the PRB chairman or vice chairman and four l

members. The PRB meets at least once per calendar month.

The PRB is specifically responsible for the following:

A. Review of:

1. Procedures that establish plantwide administrative controls to implement the quality assurance program or technical specification surveillance program.

2. Procedures for changing plant operating modes.

3. Emergency and abnormal operating procedures.

4. Procedures for effluent releases of radiological consequence. 16

5. Fuel handling procedures.

B. Review of:

1. Program required by Technical Specifications.

2. Proposed procedures and changes to procedures, equipment, or systems that involve an unreviewed safet estion as per 10.4 CFR

4 ;<.5 0 . 5 9 .a; ens -to sysbems er C. Ress.ew e 5 r e pasffe.atec.+e nut w ef 3eaoe m r ,rafe ty.

B$u f f m eafof Review t aproposed tests and experiments that affect 17 O6 nuclear safety.

E g. Review of proposed changes to the Technical Specifications. bl Jr e pedim otut fo d rd 3 F E'. Rcvica of-the rcport--of the Investigation of~re g9o violations of the technical specification that coverhinj evaluation and recommendations to prevent recurrence. eeeral De report is to b e, fcewardd to +ke Vice presiA,4 %d gPe'*U ^5 C, [. Review of all reportable events. "Q*h "p"{

H pf. Review evaluations of plant operations to detect potential nuclear safety hazards.

I EI. Performance of special reviews, investigations, or analyses and reports thereon as requested by the GMVNO or the Safety Review Board.

Amend. 16 4/85 13.4.1-2 Amend. 17 7/35 9

VEGP-ESAR-13 J )f. Review of the Security Plan and implementing procedures and submittal of recommended changes to the GMVNO.

X /. Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the GMVNO.

L/. Review of any accidental, unplanned, or uncontrolled radioactive release in excess of 1 Ci, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci for noble gases or 0.02 Ci of radiciodines for gaseous effluents.

The PRB's authority is as indicated below:

A. Recommend in writing to the GMVNO approval or 16 disapproval of items A through D above.

B. Render determinations in writing with regard to whether or not each item A through E above constitutes

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an unreviewed safety question.

C. Provide written notification within 24 h to the vice president and general manager of nuclear operations and the Safety Review Board of the disagreement between the PRB and the GMVNO; however, the GMVNO shall have responsibility for resolution of such disagreements.

at The PRB will maintain written minutes of each meeting that, a minimum, document the results of the PRB activities. Copies 17 of these minutes will be provided for the vice president and general manager-nuclear operations and the safety review board. Further details of the activities and duties of the PRB are described in plant procedures.

1 Amend. 16 4/85 13.4.1-3 Amend. 17 7/85 0368V

VEGP-FSAR-13 13.4.3 INDEPENDENT SAFETY ENGINEERING REVIEWS An independent safety engineering group (ISEG) will be established prior to initial fuel loading.to perform independent reviews of plant operations with emphasis on improving plant safety.

13.4.3.1 Composition +he SeMor- Vice. pred de nl.- bdce op eraM ons ikrou',th 1 The ISEG will be .:omprised of minimum of five qualified individuals who will report t the manager-nuclear epor2tienc analysis.in the corporate ^#fira. perform-nce on4 13.4.3.2 Qualifications ISEG members will have a bachelor's degree in engineering or applied science with a minimum of X years 2 experience in that fheir field, including at least 5 monthc nuclear experience.

t year 13.4.3.3 Responsibili tie s The ISEG will be responsible for:

16 A. Review of plant operating characteristics, NRC issuances, industry advisories, and other appropriato sources of plant design and operating experience information that may indicate areas for improving plant safety.

B. Review of selected plant activities including maintenance modifications, operational problems, and operational analysis, and in the estabilshment of programmatic requirements ftjr plant activities, 'The ISEG will develop and present fletailed recommenda*:or.

to the atpropriate level o f tn n W]"" " r.t f o r imp ro ~/< ~,

such as mvisions to procodur<: t# luipment moditt: ations.

C. Maintaining surveillante of plat.f operatim.- otrl maintenance activities to proviilh j ;Hntinti i w verification that these activitios atu ppFt,winmi correctly, and th48 human ettot are t o du :. n d a s for a-p! e +!n l'  !:

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< e pi ' r111 13,4.3-1 Amend. 16 4/85

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. ADMINISTRATIVE PROCEDURE DESCRIPTIONS I

Insert 13.5.1.1 A. Procedures for Preparation, Review, and Control of Procedures These procedures establish the controls for the preparation, review, and control of plant. procedures which cover activities as described in Appendix A of Regulatory Guide 1.33, Rev. 2.

Included within these procedures are provisions to ensure that new or revised procedures are reviewed for adequacy by appropriately qualified personnel other than the originator. In accordance with these procedures, a reviewer shall establish knowledge of the applicable requirements for a procedure and shall verify the proper incorporation of these requirements in the procedure; additionally, a reviewer shall assess whether the procedure or procedure revision potentially involves a change in the VEGP Technical Specifications or an unreviewed safety question. 2 :r: N 7:1"i::t?:- Of "? n:C r #-

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m:h;11 _  ;;cd ./, ".::: :h::h'i:t: Ch:l'  ::: r: th:t re'. i r:: r: 2 r

" th: : bj::t ... rier# ; the precedure: tMy li 1r n'!:d;; C : '" "

= J r. nd "" th:; :.. . : :d q :t: rderrt " diag C t% ;m Tm. The acceptability of procedure reviews is assured by tbevleu and approval of the review by the responsible VEGP Nuclear Gperations department hecds; the experience and education on an individual basis that qualifies department heads to perform this approval of procedure reviews is delineated in FSAR Table 13.1.2-1

" Resumes of Onsite Supervisory Personnel." Nuclear Operations department heads shall further ensure that procedures described in FSAR Section 13.4.1 are forwarded to the Plant Review Board (PRB) for additional reviewj T.n SW

& The General Manager - Vogtle Nuclear Operations (GMVN0) has ultimate responsibility for all plant procedures. Provisions of these procedures establish the GMVN0 as the approving authority for procedures which establish plant wide administrative controls (which implement the Quality Assurance Progrcn and the Technical Specifications Surveillance Program), for Unit Operating Procedures (U0P's), Emergency Operating Procedures (E0P's), Abn: ^ - ' Operating Procedures (A0P's), procedures for implementing the Sec_- < Plan, the Emergency Plan, and the Fire Protection Program, and Fi Handling Procedures. Nuclear Operations department heads are established as the ;oproving authority for other procedures covering activities within the~ area cf responsibility, f Additional provisions of these proce: ares exist to ensure trat changas or revisions to procedt.ms ae reviewe. and approved in ac ordance with the same administri:ive controls _ sed for review and Eproval of new procedures. A prc ision is made t: ensure : hat plan: ;rn dures are reviewed at least i =ry : years t a knewledgeable m:- ' dual to determine whether -

es are nec ;a ry or desi ra d e. Also provisions exist to e- e :nat proc, ares, once ap: avec. are distributed appropriatel; o t*:a t only ne most current :rccea res are used by plant personn:

Controls for the pr ' ra . review ar- approval of Ir. ia' 'est Program Procedures are aescrit ~ n FSAR Se nion 14.2.2.

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Insert A to 13.5.1.1.A For procedures not forwarded to the PRB, reviewer's will meet requirements of Section 4.4 of ANSI N18.1 - 1971 for applicable disciplines. For those disciplines not described in Section 4.4 of ANSI 18.1 - 1971, the reviewer will have a minimum of 5 years experience. A maximum of 4 years of this 5 years may be fulfilled by related technical or academic training.

Reviewers of QC inspection procedures shall meet the requirements of Reg.

Guide 1.58 Rev. 1, as described in FSAR Section 1.9.58. Also, those procedures not forwarded to the PRB and impacting another department's area of responsibility, shall be forwarded to the impacted departments for their review.

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