ML20099G751
| ML20099G751 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/20/1984 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 9455N, NUDOCS 8411270424 | |
| Download: ML20099G751 (31) | |
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Commonwsalth Edison one F ast National raza Chscago ilnno's Address Reply to Post C' ce Box 767 Chicago Ohnois 60690 November 20, 1984 ["l x '
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Mr. R. C. DeVourg, Director -
j.;
Of fice of Inspection and Enforcement LA ' -
U.S. Nuclear Regulatory Commissiol '
Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Independent Design Inspection NRC Inspection Report Nos. 50-454/83-32 References (a): October 1, 1984 letter from T. R. Tramm -: - .. -
to R. C. DeYoung . .
(b): October lo, 1984 letter from J. Nelson Grace to Cordell Reed .
(c). October 19, 1984 letter T. R. Tramm #
to R. C. DeYoung
Dear Mr. DeYoung:
N "
This letter provides additional information regarding the actions taken in response to the NRC's Integrated Design Inspection (IDI) at Byron. The information presented here supplements that f provided in reference (a) to address the NRC comments in reference ,
(b). '
Attachment A to this letter addresses the Staff comments regarding improvements in the A-E's documentation of the use of ~
engineering judgements and the review o f FSAR changes. It explains .
how the S&L QA program complies with Regulatory Guide 1.64 and ANSI N45.2.ll with respect to the documentation of design activities, especially the documentation of the design basis and engineering judgements. It also describes the manner in which S&L's engineers "
are trained in these procedures, particularly the procedures .
relating to engineering judgement and design change control.
/
Attachment D to eference (c) partially addressed the NRC comment regarding the process of FSAR Ieview and revision to reflect design changes. Additional actions have been taken. Since, and as -
a result of, the Byron IDI and IDR, project personnel are more aware -
of the necessity to update the FSAR to reflect the design when ' --
design changes are made. The numerous correspondence and discussions relative to the subject has reinforced their on the job training relative to updating the FSAR. The subject has also been discussed and emphasized at meeting where both project and support l.
personnel have attended.
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A Project Instruction under development for post fuel load 2.b - T yY ' . ' G'N design changes will reinforce the need to update tha FSAR when } ; .Y"." f f #' . '
design changes are made, by specifically requiring that the design change be evaluated for potential FSAR revision.
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The NRC also requested additional details regarding the f,c5,-g) A' if i-f . 7',,
auxiliary building flooding analyses which were summarized in -
Attachment B to reference (c). Attachment B to this letter contains ky.pf;; Cl the documentation of this analysis and identified the disposition of items identified during the reviews. [ . . [Y.h
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Please direct further questions regarding these matters to (; *i. . l,', ki.f : l this office. x' , '.: .
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One signed original and fifteen copies of this letter and t .'.C4 the Attachments are provided for NRC review. O sv. .fi.R s v, .;
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- A'"TACHMENT - F A / '
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COMPLI ANC E OF TH E' 'S ARG ENT ' & LUNDY' QUALITY ASS'URANCE PROGRAM' .
, AND PROC EDURES WITH ANSI N45.2.ll AND RBGULATORY GUIDE 1.64
[ ha;j WITH RESPECT TO DOCUMENTING DESIGN ACTIVITI ES.
The^Sargent &iLdndylQuality Assurance' Program which.is.-
described in-the. Topical Report SL'-TR-1 A, Rev,. 6, has been-approved ~by1the Nuclear Regulatory Commission as meeting the
- criteria of Appendix B:to 10CFR Part 50. :The.. Topical Report-
. stat'es'that S&L is committed - to meeting and implementing the
- applicable / provisions'of-Regulatory _-Guide 1.64, Revision 2,x June 1976, _ Quality Assurance Requirements. foro the Design of L -
Nuclear Power Plants (ANSI N45.2.11, Quality Assurance Requirements for the Design of Nuclear PowerLPlants) .except'
- as the. provisions may be modified by a commitment?in an:.
applicable SAR.
The following is'.a list of-pertinent sections of the S&L QA
-x' Program Topical Report that provides examples of how the
, pertinent sections of MISI N45.2.ll are addressed:
_ Pertinent-Sections-of ANSI N45.2.11 Section 3 - Design Input' Requirements Section 4 - Dasign Process
-Section 5 - Interface Control Section 6 - Design Verification
( Section 7 - Document Control 4
Section 8 - Design. Change Control-
+ S&L QA Program (Topical Report SL-TR-1A, Rev. 6)
Section~01, page 01-3, lines.09 through 19
+
Section 02, page 02-2, lines.13 through 22 Section 02, page 02-4, ' lines 01 through .16
- Section 03, page 03-1 lines.01 through 34 ~
' pages 03-02; 03-03; 03-04; 03-05;103-06; 03-07 Section 04, page 04-1, 04-2, 04-3 and 04-4.
h We are also attaching for your information Table 0.2.04-1
! " List Of General'Ouality Assurance Procedure" from the Topical Report. The following GQ procedures address the
- following pertinent sections of ANSI N45.2.ll
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GO Procedure- Pertinent' Sect' ion of ANSI N45.2.ll 3 ~ 4. 5 6 7 8 -
GO 3J01 x x x x x gf GO.3.02 x -x .x x J GO 3.03. x -x x x x GQ 3.04 x at -x x x x-
'GO 3.05- '-x- x x , x. . x-
, GQ 3.06 x x GO 3.07 x x x- x x x GQ,3.08 x x x x x
, GO 3.09- x x x x x GQ 3 10 x x x ac x- x
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GdQ ' 3 . l l - x x x x. x GO 3.12' x .x GO 3.13 x x- x x. x x m GO 3.14 x x?
GOL3.15 x x x x x x
. GO.3.16 x x x x -x x GO 3.17 x x x x e x . x GO 3'.18 x x -x x x x.
GQ 16.03 x ac x- x The S&L Quality Assurance Program provides for control of-S&L design and procurement activities which af fect the.
quality of safety-related nuclear power plant structures,-
systems and compenents. It is' S&L's policy' that designs be in accordance with appliable quality assurance requirements
{' and thatf design activities be procedurally controlled and documented. This includes training of personnel in quality--
related S&L activities.
In addition to thelpA procedures, the design of structures, systems, and components is planned and controlled by S&L Department Standards, Divisional Procedures and Project Instructions. , Design processes are prescribed, accomplished and documented in accordance with procedures which establish the responsibilities -and interf aces of design disciplines.
Design procedures for control of changes, additions or deletions in design information require documentation -and-approval. The appropriate engineer is ch~arged with the responsibility for defining other design documents af f ected by the change,and for resolving . and coordinating changes from other disciplines whose design is af fected.
Sargent & Lundy uses a system of planned and periodic audits 9
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3-of activities, records and facilities to verify compliance with, .and to assess the effectiveness of, the-yarious aspects -of the S&L Quality Assurance Program and the -
implementing procedures. As part of the auditing . process, samples of pertinent design-documents requiring independent reviews are taken.
-II . - DOCUMENTATION OF DESIGN BASIS AND ENGIN EERING JUDGM ENT Sargent & Lundy has addressed the need for documentation of
. design work as follows:
, QA Procedure GO-3.08, Design Calculations, contains requirements for the proper documentation of design basis includi ng assumptions, formulae and steps used in the analysis. 0A Procedure GO-3.17, Design Information Transmittal has been issued to formalize the transmittal of design information between project team members in various design disciplines. The procedure covers any design input which is not already addressed in existing standards or procedures. It requires documentation of the basis for design information including identification of design input which is preliminary.
A nonconformance review program was initiated three years ago to identify trends. The Trend Review Report is issued by Quality Assurance Division every three months, identifying the nonconformances cited during the previous 12 months. This report addresses trends and recommends corrective action. In the last four Trend Review Reports, i the subject, " documenting engineering judgment" was addressed. The corrective actions recommended in these reports were implemented. ..
The use of enginering judgment is specifically addressed by the three engineering disciplines through their respective departmental standards on calculations, SAS-22, MAS-22, and ESI -2 5 3 . These standards provide the requirements for documenting engineering judgment and permit the use of engineering judgment under the following conditions.
Engineering judgment may be used when it is evident that the design meets the appropriate criteria by a substantial margin. Engineering judgment may be used in repetitive calculations for similar designs by referencing previously reviewed and approved calculations for the same project.
Documentation shall include a discussion of differences
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/shall 1be referenced by', calculation number, 'and; revision. ,
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Engineering: judgment mayrbe :used when making revisionsa to?
approved, calculations-'iffittis evident that-thelrevision Tdoes not0 affect.the final calculation, and.ifiit is1 evident f(rom the .previously prepared : calculations : that ' design' limits .
are below the-'allowables. The' impact of the. revision ~on the
~
- finalL design- is ' required to be - documented.
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The reviewer of-a - calculation may use ' engineering judgment.
Lwhen' making comments -if it is evident that his comments'do not affect the end result of the' calculation. The basis-for engineering judgmentiis . required to be1 documented to permit verification of the logic and adequacy of the judgment.
III . Training i-r Three~Sargent's Lundy QA Procedures address the' required training of engineers engaged in thendesign of nuclear _
facilities.' .These are discussed below:
- 1. Procedure GQ-2.04 describes the ' training ' system i conducte'd by the QA Division:in the Quality Assurance Procedures. This training covers l QA Procedures GO-3.08-
)' on' calculations & GQ-3.'17 on 'Desig n 'Information -
1 Transmittal, discussed in Section II.above.
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2.
Procedure GO-2.05 addresses the training to ' be 'given ' by i
! each department in its standards and procedures. A'
[ discussion of this training as it af fects engineeirng -
{ judgment and review .of design ' changes is given below.- ,
3.
Procedure GO-2.07 addresses training ir Project Instructions. This training is also given by the.
Engineering. Departments and is discussed beldw. t i
, Department Trai ni ng a
! Trai ni ng in Department Standards is performed to training i
procedures in each engineering department.
{ A. Tra ini ng in the Documentation of Eng i nee ri ng Judgment-j.
In the Structural Engineering Division (S ED), a memo i j
has been issued to all individuals currently performing .
i
!. quality-related activities.
l This memo contained the i more judgment.
detailed requirements for the use of engineering
' Each individual receiving this memo was.
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instructed to document by signature that he has become familiar with and understands the revision to standard SAS-22 addressing ongineering -judgment. The memos are retained on file to document this training. : Revisions to this standard is also discussed in the SED
, Supervisors Technical Meetings and summarized in' the
, meeting notes which .have broad distributton within S ED.
The supervisory staff on all nuclear projects have held meetings with project personnel to review the detailed requirements governing the use of engineering
. judgment. Attendance sheets were signed to document attendance at these meetings.
In the Mechanical Department, a generic training program was established by Mechanical Department Standard MAS-8 issued in February 1984. This standard requires Mechanical Divisions performi.ng quality-related activities (other than-those governed by project unique procedures and instructions) to have a documented -divisional training program. One aspect of the divisional program is to prepare an outline identifying the standards and procedures governing each individual's work and the need for training in these standards.
Each Mechanical Division performing quality-related work has prepared an outline as required, and MAS-22 (addressing engineering judgment) or its equivalent has been identified on that outline as one of the standards that individuals who prepare, review and approve safety-related calculations must be trained in. The actual training is now 4.n progress and will be ongoing as new personnel are added to the list. The training consists of the Supervisor or his Designee di'recting the individual to read MAS-22 or its equivalent, and to discuss any questions that he may have with the Supervisor. The Supervisor also observes the work of the individual to determine that he has attained adequated knowledge of the procedure or standard. Whei this has been accomplished, the Supervisor documents the individual's proficiency and sends this documentation to the Divisional Training Coordinator for record purposes.
In the Electrical Department, documented training has been conducted dealing with the use of engineering judgment when preparing calculations. ESI-253 has been e
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circulated through the ' Electrical Analytical Division and the Electrical Project Engineering Division to the responsible engineers. All employees responsible for performing Junction Box Calculations have received a.
revised copy of EDSI-77 which incorporates the concept
. of engineering judgment. Engineering judgment has also been the subject of intra and interdivisional meetings to emphasize its use.
B. Trai ning in the Review and Control of Design Changes fin addition to the Quality Assurance procedures governing changes to drawings, specifications, calculations, and Engineering Change Notices, the processing of design changes is the subject of. a number of' project instructions. Personnel performing ' design verification are trained in applicable standards and procedures. . Training in design verification activities
, is covered by both generic and project unique training programs.
An individual is required to be retrained whenever his responsibilities change or are substantially af f ected by a revision to applicable standards and procedures.
Records are maintained to document the successful completion of all required training. Trai ni ng in Project Instructions is generally conducted in the project team meetings which are attended by representatives from cognizant divisions and departments. In these meetings, the project instruction is introduced and discussed. This is documented in the meeting notes. The attendees at this meeting are usually the lead personnel from the various divisions. It is the responsibility of those lead personnel to carry the message back to the pe'sonnelr under their supervision and to instruct those personnel in the requirements of the project instruction.
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ATTACHMENT B Calculation Sheets Which Document The Reviews of Auxiliary .uilding Flooding 9455N l
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EESITN INFORMATION TRANSMITTAL gc, l 5 ARGENT ELUNDY !
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( ' ', O SAFETY-RELATED D NON-SAFETY-RELATED DtT BY-EPED-0012-l* CLIENT Ceco Page 1 of 1 j STATION Byron 1& 2 To _M. S. Leutloff - 22 UNIT (S) PROJECT NO(S). 4391/2 hp V" J. D. Recan _EPED h_ /O -l2- M Responsible individual ' " " " * " " Division Resp 0,nsible if dividual's signature issue date
- STATUS OF INFORMATION (this information is apprNed for use. Design information, approved for use, that contains assumptions or is preliminary or requires further verification (review) shall be so identified)
.$ r% This information is approved for use. No further verification
.if!.35)* is required. - *
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ha jc? IDENTIFICATION OF THE SPECIFIC DESIGN INFORMATION TRANSMITTED AND PURPOSE OF ISSUE (list any supporting documents attached to DIT by its title and revision and/or issue date) Attachment "A" identifies all safety-related electrical equipment which is located below the flood level within the flood zone identified. The flood levels used to determine the af fected equipment are those identified in the Auxiliary Building Flood
.P. ... Level Calculation (Calc. No. 3CB-1281-001), Rev. 1, dated 3-1-84.
i,.; :.g$ Only safety-related electrical equipment is listed. l l w ,
*This DIT supersedes DIT-BY-EPED-0012, dated 7-19-84. The revision f., :;- of the above calculation has been corrected.
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.g.i ., B ASIS FOR INFORMATION
_k if Calc. no. N/A Report no. N/A I.O.M. from T. kip e#'s" N Y. G. Gogliotti, dated Rev. and/or date Other 4-21-94, 5-10-94 and 6-11-84. DISTRIBUTION CC: D. L. Leone /W. C. Cleff'- 22 (1/1) K. J. Green - 22 (1/1) i
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4: l SARGENT i LUNDY
~~~~--m DESIGN INFORM ATION TRANSMITTAL I C5 SAFETY-RELATED C NON-SAFETY-RELATED DIT RB-CID '006- A Page 1 of 12 CLIENT Comconwealth Edison Comocny )
STATION Byron /Braidwood UNIT (S) 1 & 2 To" J. Grun: .2n - I PROJECT NO(S). 4 331/4 39 2 /4 68 3f.16 S4 c ] C R. P. O rk f rit: CID %
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9/25/34 Responsiote incivi::ual ' ' * * " " Division "Resoonsible inciv}duars signature issue da:e STATUS OF INFORM ATION (this information is approved for use. Design information,2coroved for t se, that contains assump::o..s or is preliminary or requires further verification (review) shall te so ident.' eci This information is approved for use. g .a - C 3- lDENTIFICATION OF THE SPECIFIC DESIGN INFORMATION TR ANSMITTED AND PURPOSE OF ISSUE [ (list any scoporting cocuments attaenec to DIT by its tit:e anc revision and/or issue cate) Refer to DIT-BB-CID-0006. Revisien made to page 5 which corrected instrument panel nur.bers , on M-828-13, zone 53-133. h U., l 3 , = - l d a 2 5o 0 E BASIS FOR INFO 9 MAT!ON
- 2 Calc. no. 4'A Report no. N/A Rev. and'or cata Rev, aric/or ca:s l
C tt.er NC W DISTRIGUTION - W. C. Cle f f P
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DIT- BB-CID-0006 CJ SAFETY-RELATED O NON-SAFETY.RELATED 5 CLIENT Commonwesilth Edison Company Page _1 of 12 STATION Dyron/Braidwood 1&2 To J- hWM UNIT (S) PROJECT NO(S). 4391/439224683/4684 - C R. Orkfritz C&ID Q g g/yffy Responsible individual " * * * * * ' " " Division ' 'R8sponsibic ipcivj3ual's signature issue date STATUS OF INFOR*.!ATION (this information is approved for use. Design s'nformation, approved for use. that contains assumptions or as preliminary or requires further verification (review) shall be so icentifieo) This is approved for use. N
~.- 'I IDENTIFICATION OFTHE SPECIFIC DESIGNINFORMATlON TRANSMITTED AND PURPO3E OFISSUE (list any supporting documents attached to DIT by its titie and revision and/or issue date)
C&ID has reviewed the auxiliary building ficod levels versus the mechanical instrument location drawings with the results attached. There are no problems with safety-related instruments found to auxiliar;' flooding. / 5 J., e . e . E 2 5 . O =. O BASIS FOR INFORMATION E
?. d Calc. no. Report no.
Rev. and/or dato Rev, anc/or date Other ( - DISTRIBUTIOld W. C. C1eff 1:
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W W ENT & LUNDY i INTEROFFICE MEMORANDUM b[ Fna, D. H. Flens - 31 (X3901) _ page Auoust 1, 19?4 Project No. 4 391/ 2 ; M 3 I e ;- M Dept /Div. Mechanica1/HVAC Sp,c, go, File No. Page No. 1 Oknt CECO se, Byron /Braidwood Unit 1& 2 kbject HVAC Auxiliary Building Flood Level Impact Report To: K. J. Green (1/1) - 22 cc: D. L. Leone (1/1) - 22 W. C. Cleff (1/0) - 22 J. Grundman (1/0) - 22 G. C. Jones (1/0) - 22 D. C. Soni (1/0) - 20 A.M. Bizarra (1/1) W. B. Paschal /S. N. Planjery (1/0) - 31 E.,G. Hibbard (1/0) - 31 Attached is a copy of HVAC Calculation HDI-02-BB, Revision 1,
, dated 07-27-84, entitled " Impact of Auxiliary Building Flood Levels on HVAC," which was prepared per your request.
A list of our assumptions used in performing the evaluation is provided on page 2 of this report. A summary of our report is also provided on page 13. If you have any questions, please contact me. DHF:alj Attachment
%F601 11101
Y . . a* DOCUMENT ISSUE SUYJ1ARY S!!EET _..s Client: CM# / -
' Doc. ?:o.: NOI-42 ~Oirl Froject: P.gfrzed /BM'N " novicien: 1. -
Pre]cet No.: 931// g fd83/f-o* Nuclear Safety-Related Respcncible Divieles.: BVpc Equ ip- ent No. : IIIC IDd0X E0*: O Nuclear Non-Safety-Related Page I of / $ ~ 8./ C Fossil , ,
Title:
Tvenc.y .5 Aux.Gt.94. boo LEysu on gvAc. Eevision Date Revtsed Preparer Method of Revicwer/ Approver /. Nu--b e r p Review Date D .te O Q.a.f%f A i" < H0 v.. R. > L d % %/ %'v,- 7/n/W As t- . teva"-
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