ML19207C192
| ML19207C192 | |
| Person / Time | |
|---|---|
| Issue date: | 06/29/1979 |
| From: | Donna Anderson, Hale C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19207C190 | List: |
| References | |
| REF-QA-99900525 51200, NUDOCS 7909100136 | |
| Download: ML19207C192 (9) | |
Text
U. S. NUCLEAR REGULATORY COPMISSIO 4 0FFICE OF I:SPECTION A!iD EtiFORCEMEi!T REGIO:1 I'!
Report !!o.
99900525/79-02 Progran 0o. 51200 Company:
Gilbert /Comonwealth Ccmpanies 525 Lancaster Avenue, P. O. Box 1598 Eeading, Pennsylvania 19603 Inspecticn at:
Jackson, Michigan inspection Conducted:
June 19-22, 1979 Inspector:
[ Oh-
? b d[f//f D. 'G. Anderscn, Principal Inspector Date Vendor Inspection Branch Approved by:
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C. J Hale, Cnief, Program Evaluaticn Section Cate' Vend r Inspection Branch Surrary Ins:ection en June 19-22, 1979 (99900525/79-02)
Areas Inscected:
Implementaticn of Title 10 CFR 50, Apcendix B, including design inspeccicn and acticn en previcus inspecticn findings.
The ins;ec-tien involved t..enty-nine (29) ins;ection-hours on site by one (1) US :RC inspector.
Res ul ts :
In the t.so (2) areas inspected, no deviaticns or unresolved items were identified.
7909100 /3 6 61 an 3
2 CETAILS SECTICN (Prepared by D. G. Anderscn)
A.
Persons Contacted M. B. deEstrada, Structural Engineer
- W. E. Kessler, Project Manager
- R. A. Lang, Project Licensing Engineer
- A. D. Naya'c9adi, Supervising Piping Engineer J. C. Norman, Manager, Ccm: uter Operations B. S. Russell, Manager, A, lications Programming V. J. Shah, Senior W.ilan1
.ngineer
- P. Thacker, Project Quality Coordinator C. R. Wi therell, Structural Engineer
'Incicates attendance at the exit meeting.
B.
Action en Previous Inscection Findinas (Closed) Ceviaticn (Report No. 77-01):
The Engineering and Construction Budget Management Manual for the Erie Nuclear Plant had been issued without approval by Chio Edison.
The inspector assured that the corrective action and action to prevent recurrence as addressed in the Gilbert /Cccmonwealth letter of response dated September 23, 1977 had been ccmpleted.
The inspector reviewed subsequent revisicns to the manual and assured that each had been approved by Chio Edison as re q ui re d.
(Closed) Ceviaticn (Report No. 77-01):
The Cesign Veri fication Schedule had not been updated as required.
The inspector assured that the Cesign Verificaticn Schedule had been updated as indicated in the Gilbert /Ccnmenwealth letter of response dated Septembar 23, 1977. The insoector also reviened a memorandum dated September 21, 1977 to all supervising engineers en the Erie Nuclear Project wnich addressed the necessity for maintaining the Design Verificaticn Scnedule current.
C.
Cesign Inscection 1.
Cb iecti ves The objectives of this area of the. Tspection were to select a single corponent, system, structure, or major part of cne of these and verify that; Cesign inputs are identified and include all apclicable re-a.
quirements; documented; reviewed and approved; s;eci'ied on a tirely basis and in necessary detail' prepared, prccessed,
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3 and controlled in accordance with acplicable procedures; accurate in specifying design requirements, carticularly design ccdas and standards; and distributed to those respon-sible for preparing producticn designs and associated docurents.
b.
Cesign calculations, and their review and approval, have been performed as prescribed by peccedures.
Final design documents have accurately transcribed design c.
input in accordance with procedures.
d.
Internal and external design interface responsibilities and activities have been performed in accordance with procedures.
Verification of the design has been properly and effectively e.
perfor ed as prescribed by precedures, including design review (including checking), alternate calculations, and qualifica-tion testing where applicable.
f.
Changes to the design, through all design activities from input to output, have been performed in accordanca with pro-cedure requirements.
g.
Cesign corrective actions have been applied, as necessary, to the design for applicable activities in accordance with procedures.
h.
The design dccument control system is effective for the item design documents in accordance with procedures.
i.
Procurement documents have been prcperly prepared for the iten in accordance with procedures and include the necessary dccuments.
2.
"ethcd of Acccrolishment The oraceding objectivies were accomplished as follows:
a.
A review of the Preliminary Safety Analysis Report for Chic Edison / Erie "uclear Plants, Units 1 and 2, Section 17.3, Cesign Control, which identifies the requirements impcsed upon Gilbert /Ccmmonwealth related to the cesign process.
The design process related to the Erie "uclear Project is defined, implemented, and enforced according to the follcwing p ro cedu res :
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4 Cesign Centrol Procedures, DCPe 1.C5, Classification of Structures, Systems, and Ccrpcnents ; DCP= 1.10, Cesign Input; DCP3 1.15, Layout Crawings; CCP9 1.20, Calculations ;
CCP# 1.25, Fluid System and Instrument Lcep Diagrams; CCP= 1.30, Crawings; CCPd 1.25, System Lcgic Ciagrams ;
CCPd 1. ~0, Cne Line and Relay Diagrams; DCPF 1.45, System Cesign Description; CCPF 1.50, Procuction Ccrputer Program Cocumentation and Certification; CCPd 1.55, Cesign $;ecifi-caticns for Nuclear Pcwer Plant Cccpenents; DCP5 2.05, Cesign Veri ficaticn; CCPd 2.10, Engineering Change tiotices; DCP# 3.15, Project Pecords Control, CCPd d.10, Technical Scecificaticns and Bills of Material', DCPS 5.10, Project I!anagement Fanual',
CCPd 5.30, Technical Support Services; and CCP4 6.05, Safety Analysis Reports.
The inspector also deternined that the folicwing document contains certain exceptions to the CCP's which can be considered as project unique procedural require-ments:
Engineering and Constructicn Sudget Management "anual, Chic Edison Ccmpany, Erie Nuclear Plant, Units 1 and 2, Comenwealth Associates, Inc. Revisien 6, 2/28/79.
b.
The inspector verified that design inputs for the feedwater system and the auxiliary feedwater system are contained in the following documents ;
0-CCO-10-004, Project Cesign Criteria, Erie t!aclear Plant, Units 1 and 2.
In particular, seismic loads are contained in secticn 2.6.2.3.1.
0-421-01-01-0, Systen Design Descriptien, Auxiliary Feedwater System, Ohio Edison Corgany/ Erie Nuclear Dlant, Units 1 an: 2.
EN ', GI/CC".-135, Earthquake Peturn Frequency Analysis, '.!codward/
Clyda Ccnsultants, 6/23/75.
0 a20 al-01-0, System Cesign Cescriptien, Feecwater Sys tem, Cnio Edison Ccmpany, Erie Nuclear Plant, Units 1 and 2.
0-444-41-01-0, System Design Cescription, Condansate Storage and Makeup Syscen, Ohio Ediscn Ccrcary, Erie i,uclear Plant, Units 1 and 2.
c.
The inspector verified that the folicwing design calculations had teen performed and verified acccrding to procedures:
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b
5 (1)
Calculaticns 0-CCO-22-20-0-04, Design basis for the seismic analysis of the auxiliary building complex,1/2S/77.
0-140-22-09-0-01, Response spectra for the auxiliary building cor. plex, 6/13/77.
0-140-22-04-0-03, Final seismic model for the auxiliary buil ding, 3/16/ 77.
0-140-22-C9-0-04, Floor response curves for the auxiliary building complex, 2/15/77.
0-1d0-22-06-0-03, Seismic analysis for the auxiliary building, 2/9/77.
C-140-22-C6-0-01, Dynamic analysis for the auxiliary building corplex, 4/11/77.
(2) Computer Programs DY"AL-A Fortran I'! Ccm:: uter code which uses the super-positicn of normal ncdes technique to obtain system respcnses of a structure.
The folicwing are DYNAL accessary codes:
0-130-22-03-0-01, SPRINGS-A Fortran IV computcr program to compute reduction factors for the soil springs used in seismic analysis.
0-130-22-05-0-01, NRC-A Fcrtran IV computer ccde which calculates spectral accelerations bases en the ERIC Nuclear Plant design respcnse spectra to meet Regulatory Guide 1.60 requi reren ts.
0-120-22-05-0-01, CAMPER-A Fcrtran IV ccmouter code which calculates the weighted modal darping using an adaption of the Roesset method.
0-130-22-C8-0, SOR7ER-A Fortran I'l ccmputer code, nich sorts modes and determines tne extent to which natural fr2quencies be included in resconse spectrum computation.
C-130-22-09-0, UPLIFT-A Fortran IV ccmputer code which evaluates the uplift and maximum scil pressure of a circular 51ab/ soil system cue to seismic leads.
T?IFE-A special purpose ccmouter program capable cf per-ferming static and dynamic linear elastic analyses cf power related piping systems.
The dynamic analysis cption includes (1) frequency extracticn, (2) res;cnse spec: rum, (3) time history medal superpositicn, anc (1) time history direct integratien methods.
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5 d.
The folio. sing final design docurents were reviewed for in-corporaticn of input:
Preliminary Safety Analysis Peport, Ohio Edison Company, Erie Nuclear Project, Units 1 and 2, Chapter 3.7, Seismic Design.
Crawings:
Ei;C-0-421-41-05-001, Auxiliary Feedwater System Schematic, 3/6/73.
EMB-0 121-51-03-C01, 002, 003, Auxiliary Feedwater System Logic, 3/6/78.
ENG-1-420 al-02-C01, 002, Fluid System Diagram-Feedwater System, 10/2J/75.
EN3-1 all-51-02-001, 002, 003, Instrument Loop Diagram Conden-sate Stcrage and Pakeup System, 2/13/78.
ENG-1-414-41-02-C01, Fluid System Diagram-Condensate Storage and "akeup System, 10/23/73.
ENG-1444-51-09-C01, 002, Logic Diagram-Condensate Storage Sys tem, 2/13/78.
ENG-1 a23-41-02-001, Fluid System Diagram-Steam Generator Feed-water Pump Turbine Steam Supply, 9/27/78.
ENS-1-421-51-02-001, CO2, Instrument Loop Diagrac-Auxiliary Feedwater System, 9/12/77.
ENG-1421 al-02-001, Fluid System Diagram, Auxiliary Feedwater System, 10/19/78.
ENG-1-421-51-09-001, 002, CC3, Lcgic Diagram-Auxiliary Feed-water System, 4/3/78.
ENJ-1-421-41-26-001, 002, 004, 005, Auxiliary Feedwater System-Auxiliary Area Pump Rcca, Peactor Euilding, and Sections.
e.
The inspector verified that for the Erie Nuclear Project that internal and external interfaces are identified in the Encineering and Constructicn Budgat Management l'anual and design cocuments are transmitted to these interfaces thrcugh the folicwing:
Letters of 7ransmittai:
EN/COM/0EC-2233, Auxiliary Feedwater System-System Cesign Cescrip;i on, 3/9/73.
EN/CCM/ CEC-1678, Feedwater System, Systen Cesign Cescription, 7/15/77.
EN/CO.M/0EC-2168, Condensate Storage and Makeup System-System Cesign Cescription, 5/9/78 EN/CCP/ CEC-2357, Auxiliary Feedwater Pumps, Pctors, and Turbines-Speci fication, 6/1/75.
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7 Ef:/CCM/ CEC-2225, E.o and One-half inch and larcer Carbcn and Stainless Steel '!alves-Speci ficaticn, 8/16/78.
EN/CCM/ CEC-3C54, Steam Cererator Feedwater Purps and Ste;n Generator Occster Feed,ater Pumps-Specification, 9/22/75.
E.N/ CC.M/ C E C-2 754, ree6iate r Featers-Speci fication, 7/12/73.
EN/CC"/ CEC-3481, kencrents to the Prelicin2ry Safety Analysis Repcrt-Erie Nuclear Plant, Units 1 and 2, 6/13/79.
f.
For each calculaticn and cencuter progran run identi"ied in C.2.c.(1) and (2) abc ze, tha following dcccentation supported design verification activities related to each:
Calculations:
(1) Cesign '!erificaticn Record and Ccver Pege.
( 2 ) Ces i en 'le ri fi ca ti on S urra r.v.
Ccrputer erograr.s:
(1) User Manual.
(2) Program Listing.
(3) '!arificaticn of line by line review of the Fortran listing, cr (4) C0mpariscn with other codes in the public
' rain.
Supporting Cocurentation:
GAI Report No.1829, DYNAL Progra: '!ari ficaticn Manual, 3/1/74 DYTML ccrpared with PRI/STAPDYNE Cctputer Program 'lerification Sumary, 3/1/74, CYNAL 'lerificaticn Run dated 3/28/77.
SPRIT;GS 'ierificatico indicated on listing dated 2/11/77.
,7t Program '.,er1rication Manual ccntaining t'..enty-six (26) ir.r benchrark problets and ccrparison cf cutput with cutput frcn ANSYS, PIPSD, and SAPIPE cn twenty-nine (29) cenputer runs, 5/15/73.
Cal culation 1-421-42-13-0-05, Pipe Stress Analysis-Auxiliary Feedwater System, cackage contains Crawing EN-1221-41-25-002, Piping !scretric-Auxiliary Feedwater Systen, Auxiliary Building, and Peactor Euilding, 4/11/7E.
NRC '!eri #ication lis ting and corpucer runs, 3/15/76.
DAFFER '!erificaticn of Lis ting, S/12/76.
SCRTER 'lerificaticn listing and corcuter runs,1/31/75.
UPLIFT /erification of Listing, 2/26/75.
The inspectar ncted that PMB Syster.s Engineering (consultant custocian for TPIPE) had identified the folic..ing errors in :ne TPIPE ccrcuter ccde and had addressed these errors to Cilbert/
Cc=cnwealth by written mercrandun:
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8 (1)
Res;cnsa spectrum analysis /rcngiccal dynamic springs, 7/5/77, (2)
Incorrect static reaction calculaticns,1/19/78.
(3)
Incensistent marber and force sign ccnsention,1/19/78.
(4)
Incorre:: tire ic:egraticn and heat transfer coefficients,
1/19/73.
(5) Modal su;erposition time history analysis affecting resequenced order of nodes and ground motion excitation, 5/7/79.
g.
The inscactor revie'..ed the folicwing design changes to assure that tney were reviewed and approved and that corrective action had been implerented where appropriate:
Engineering Change Notices :
ECN# C07, Foundaticn change in the auxiliary building, including Calculaticn 0-140-22-C5-0-98, Evaluation of changes in the auxiliary building, 6/22/79, and Drawing # ENG-0-100-22-13-0C3, Auxiliary Guilding.
ECN# 009, Fcundaticn change in the auxiliary building, including Crawing# ENJ-0-C07-70-CO-020, Structural layout drawing-Units 1 and 2, Diesel generator buildings and scuth auxiliary areas, and DYNAL ccrputer runs dated 8/18/73-Evaluaticn of changes in the auxiliary building for seismic Icads.
h.
The inspector verified that the document control system for the manuals, prccedures, PSAR, system design descriptions, croject design criteria, and ccc? uter code documentation are maintained under a numbering system which compares with the assignment listing as required by procedures.
This assures that revisions to these documents are prcrptly transmitted tc the assigned indi vi dual.
i.
The insoectcr verified that the following orccurerent docurents are pr2 pared and transmitted accceding to procedure:
Speci fications :
0-421-41-30-35, Auxiliary Feedwater purps, motors, and turbines,
4/26/78.
0-018-41-31-3S, Two and cne-half inch and larger carbon and stainless steel valves (ECO-15CO pound), 4/21/72.
0-444-al-3C-35, Ccndensate Storage Tanks, 4/26/78.
0-011-01-31-35, Feedwater Isclaticn "alves, 1/25/79.
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9 0-420-01-33-35, Stean Generatcr Feedwater Purp Turbines, 10/18/73.
0-420-a1-30-35, Stean Generator Feedwater Pumps and Stean Generator Bocster Feed.sater Pumps, 8/25/75.
0-420-01-24-35, Feecuater Featers, 5/25/78.
3.
Findings In this area of the inspecticn, no deviaticns or unresolvad items were identified.
D.
Exi t "eeting An exit teeting was ccnducted with Gilbert /Correnwealth canagement personnel at the conclusion cf the inscection en June 22, 1979.
These individuals indicated by an asterisk in the Cetails Section of this report were in attendance.
In addition, the follcwing nere present:
R. E. Bailey, Panager, Design Centrol N. R. Barker, Quality Assurance Division, General Manager M. J. Brocks, Supervisor, Production Ccntroi J. E. Cavis, Adminiscrative Manager H. E. Herbert, Cata Processing Librarian P. S. Ingebo, Manager, Corporate Services A. A. Jaeger, Project Administrator D. D. Millican, Panager, Records "anagerert R. W. Potts, Manager of Engineering D. E. Price, Asscciate Engineer, Chio Ediscn F. T. Schart, Panager, Quality Assurance Cepartment R-D. Thcmas, Project Cesign Engineer T
U. White, Project Cuality Cccrdinatcr The inspector discussed the two (2) previous deviations (Inspecticn 99900525/77-01) shich were closed during this inspection.
T'e inscector r
cutlined the scope cf this inscection and indicated that no further findings were identified during the inspection.
The inspectcr also indicated that based upon prev"cus ccrputer ccde inspections sich NRP/HQ personnel, that crganicaticns perforcing design activities can expect increased emphasis of inspecticn in the area of computer code deveiccrent, use, verificaticn, and certification.
Gil be rt/Cc~mcnweal th was encouraged to review their existing precedJre3 f0F CCTputer CCde application to assure that the eierents cf A"$1 M45.2.11 here included.
Managerent representatives cf Gilbert /Cccm:nwealth ackrculedged the statements of the inspectcr.
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