ML20202B467
| ML20202B467 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/07/1985 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML18052B537 | List:
|
| References | |
| FOIA-85-59 CP-EI-4.0-13, NUDOCS 8607100307 | |
| Download: ML20202B467 (175) | |
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'i TEXAS UrILITIES SERVICES INC.
INSTIUCTICN REVISION ISSUE PAGE DATE CONrBOLLED COPY to.
CP-EI-4.0-13 12 2-7-85 1 of 6 i
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j OJNTIOL OF SITE SCOPE STRESS ANALYSIS ACTIVITIES PREPARED BY m
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1.0 REFERENCES
f 1-A CP-EP-4.0 Design Control 1-B CP-EP-5.4 Design Verification 1-C CP-EI-4.5-22 General Progran for the Qualification of As-Built I
Ioads on Equipment and Valves l
1-D 2323 MS-200 Design Specification for all ASME Section III Code Class 2 & 3 Piping l
2.0 GENEPAL i
2.1 PURPOSE
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The purpose of this instruction is to address the necessaty control functions for stress analysis of safety class piping.
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his instruction shall identify the specific means by which the provisions of Beference 1-A and 1-B are implemente3.
2.2 SCCPE i
Wese engineering instructions cover site scope and pipe stress analysis activities. 21s piping shall to analyzed in accordance with the Gibbs & Hill Simplified Analysis Criteria or conputer j
programs (ADLPIPE or SUPERPIPE). Forms DHE-5, and DHE-14 thru DHE-22 have been developed to assist the Stress Analysis Engineer in e
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his wrk functions.
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2.3 IESPONSIBILITl 4
l The CPP Pipe Support Engineer (PPSE) is responsible for providiM technical direction and administrative guidan::e to the Technical Services Organization and the general implementation of this instruction. We Technical Services Supervisor has been delegated the responsibility of ensuring the specific'inglenuntation of the activities described herein.
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F01A-85-59 8607100307 860630 3
.l GARDE 85-59 PDR 1
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TEXAS (7fILITIES SERVICES INC.
INSTECTION REVISION ISSUE PAGE O
l CP-EI-4.0-13 12 2-7-85 2 of 6 e'
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j 2.3 RESPONSIBILITY (Continued) mere specific individuals are designated by title in this i
instruction, it shall be understood that designees may be delegated 4
to act in that capacity.
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3.0 INST W CTION
.i 3.1 DESIGN PREPARATION i
3.1.1 Chtain a mpy of the current revision of the "BRP" and any 1
outstanding "OtC's".
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- 8 3.1.2 Check the reference file for data on any valves, instruments or j
connecting equipment shown on the isometric. If none is available,
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obtain from DCC.
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3.1.3 Refer to the proper doctanent to determine design paraneters and
- j criteria to be used in the analysis.
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1 3.1.4 Refer to the appropriate section of specification 2323-4tS-46A for j
(q identification of pipe properties from the pipe specification Ns indicated in the line msnber. As a minista the following shall be 4
specified in the calculations: Pipe category, size, material, and
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- j schedule and/or thidness (pipe thickness shall be obtained fran other sources).
2 3.1.5 Refer to the piping maposite drawing referenced on the "BRP" to determine piping and equipnent located in the vicinity of the line to be analyzed.
3.1.6 Cieck the pipe routing in the field to verify possible pipe support j
locations and that piping geonstry agrees with BRP's and OtC's.
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3.1.7 2e provisions of Reference 1-D shall be inglemented as applicable.
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TEXAS (frILITIES SEFVICES INC.
INST!UC1'ICN REVISION ISSUE PME O
CP-EI-4.0-12 12 2-7-85 3 of 6 3.2 DESIG4 3.2.1 Unless specific data is given, seismic displacements at terminating equipnent are assumed negligible. Thermal displacements at ter:ninating equignent nust be calculated if this information is not provided.
3.2.2 Seismic and thern.al displacement's at interfacing piping shall be reviewed.
3.2.3 Nozzle loads on equipnent shall be calculated. Supports shall be located such that these nozzle reaction loads are as low as possible. If the calculated loads exceed the vendor allowables,
[e this shall be documented in the analysis package and in the ll systan' punch list. Discrepancies will be resolved with the vendor in accordance with Ref.1-C during final review.
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3.2.4 Small lines connecting to larger size piping may have been
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partially included as over lap in the analysis. The following rules govern inclusion in the analysis:
- "S*" 9 9' **** (""") d- *** 9'9' **** (""*"ch) 1 O
-1 D > 8":
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D 7 branch is included in the analysis d <7 branch is excluded from the analysis 1
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7 branch is included in the analysis d
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D 2 branch is exluded frczn the analysis
/ If the branch has been included in the analysis of the pipe 1,
run, an investigation shall be made to determine support requirements R
on the branch piping. Also, outside organizations may have issued support designs for the over lap area and this shall be checked.
3.2.5 Generally, interfacing between two isanetrics can be cbne by over lapping two supports in each direction for both iscrnetrics.
3.2.6 Gang supports shall be used where possible. men this is done, y
it shall be stated on the cover sheets of all involved analysis packages giving the corresponding suppxt and iscxnetric nuabers. All gang support feasibility studies shall be coordinated with the w wriate pipe support design section.
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..,'j EXAS ITTILITIES SERVICES INC.
Ih3TRUCTION REVISION ISSUE PAGE e
DATE CP-EI-4.0-13 12 2-7-85 4 of 6 i
3.2.7 If rigorous stress analysis is dswuned necessary, the conputer analysis service shall be provided by the site Stress Analysis croup.
u.j 3.2.8 All notations cn the Surpart Ia:ation Isometric shall be standard as shown below:
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'*.l DIRECTIONAL SUPPORT SPRING t
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.I SNUBSER MODIFIED RIGID ANCHOR
~.j 3.2.9 Nherever possible supports shall be nLunbered in sequence from I
one end of the line to the other. Separate support numbers 4
at the same location and shall be separated dimer:sionally as shall be given to rigid, snubber, M-Rigid, and spring supports i
shown below for ease of installation.
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3.2.10 Unless otherwise noted, the field installation tolerance on support placement is + 6".
Consequently the seisnic and deadweight span should be at least 6" under the allowable. If the support must be located more exactly, place an asterisk (*) beside the
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'IEXAS (frILITIES SERVICES INC.
INSTRUCTION REVISIN ISSUE PME i
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cATE I
CP-EI-4.0-1]
12 2-7-85 5 of 6 i
8 1
,1 3.2.10 (Continued) i cupport location dimension which will mandate an installation 1
tolerance of + 1/2". Also any mandatory axial supports located near an elbow shall have an asterisk (*) beside its location t
i di.mension.
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3.2.11 Global axis cn support location isc:netrics shall have the positive 1
"X" axis pointing north.
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3.2.12 Ioads due to relief valves shall be added to seismic loads by l
using the absolute value.
3.2.13 In the coltunn for " Support No." on Icad Sumr.ary Sheets the
- j follosing should be included
1 gi Node point, partial loads, direction and type of
' ~8 support (e.g. X-rigid, Y-snubber, X-Z rigid, etc.)
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j 3.2.14 toads on the load suninary sheet shall be rounded off to the j
higher whole nunber.
(e.g. 49.35 becomes 506)
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3.2.15 Movements shall be included on the Ioad Stenary Sheets.
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.I 3.2.16 For rigorously analyzed pipirg a note shall be placed on the j
iscinetric which reads "'Ihis ISO is canputer analyzed".
j 3.2.17 All assunttions and references used in the analysis shall be 1
documented.
3.2.18 'Ihe possible applications of "M-Rigids" are as listed in the following:
1.
Substitute Modified Rigid Supports (M-Rigid) for snubbers when the calculated thermal displacement is less than 1/16".
2.
Limited thennal stop.
3.
When "M-Rigid" is used for seismic / deadweight support applications, assure that no up-lift loading will occur; i.e.,
the upward thermal load is always less than the deadweight load.
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3.3 DESI@ VERIFICATIN 3.3.1 All open items shall be th'= anted in the systen punch list.
'Ihe analysis supervisor shall insure that these punch list items are periodically reviewed and cleaggi.
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'IEXAS UTILITIES SERVICES INC.
INSTIUCTION REVISION ISSUE PEE T
De j
2-7-85 6 of 6 I
CP-EI-4.0-13 12 1
h 3.3.2 2 e pipe stress analysis engineer shall initial and date ea d IHE-5 calculation sheet and all applicable forms in the "CAIE" Block, make a check copy of the analysis package and forward the padage to the section supervisor.
3.3.3 2e section supervisor shall assign the package to an authorized design verifier.
.e 3.3.4 2e design verifier shall make his/her connents on the check copy of the analysis package and initial and date each sheet of the check copy in the "CHKD" block. Se package shall be returned to the originating stress analyst for resoluticn of any connents.
3.3.5 Upon coupletion of the design verification, the design verifier shall conglete DHE-22 (and DHE-22A if applicable) initial and date the original of ead calculation sheet and all applicable forms in the "CHKD" and "D.V." blocks. S e package shall then be returned to the section supervisor.
y 3.3.6 An authorized engineer shall signify his approval of the analysis package by initialing and dating form DHE-14 in the approval
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3.3.7 2e conpleted package, which shall include sufficient support
..i loading data shall be forwarded to the support design group.
3.3.8 If reanalysis is required for any reason it shall be performed in the same manner as described above.
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( c_hgo D5N d I. INTRODUCTION A. This criteria was developed to qulatfy class 2 & 3 piping systems which need to meet ASME Section III code requirements but do not need complex computer analysis due to their reduced criticality and less severe operating conditions.
B. This criteria is a guide in locating and detennining loads for supports.
In certain situations where spans or loads are critical, special inter-pretations of the criteria or sound engineering judgement may allow enough relaxation in certain rules to allow the engineer to meet limita-tions for loads or spans.
II. DEVELOPMENT A. Two basic methods of seismic analysis
- 1. Time history analysis (cost =c)
- 2. Spectral analysis - conservative (cost =c/10)
- 8. Geological survey performed to determine seismology and generate a time history curve.
C. Time history curve coupled with soil analysis and structure to determine the base time history.
D. Spectra response developed for various structures and elevations.
E. All pipe cross-sections limited to same maximum dynamic deflection.
F. Most critical cross-section determined and a spectral analysis performed.
- 1. Stresses and reactions interrelated for any two cross-sections by prc,-
portionality constants.
- 2. Accuracy not sacrificed.
- 3. Yields only varying degrees of conservatism.
- 4. Adjustment to conservatism made by separating into pipe cases by build-ing spectra and weight.
G. Results of analysis appear as tabulated spans and loads with special rules and restrictions delineated in the text.
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- 1. Stress limits met by meeting span requirements for gravity, seismic and thercal, and observing limits impnsed on stress intensification factors for the various components in the system.
III. APPLICATION A. Collect all available known data.
- 3. Pressure "Q "R 1\\O
- 1. Pipe s'ize
- 2. Pipe schedule l"
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- 4. Temperature
- 5. Insulation requirements and/or heat ' tracing.
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- 6. End conditions (displacements, load allowables, etc.) etc..
(,. B. Detennine and list table values of spans, loads, maximum run lengths.
6.C.Filloutapplicabilitychecklist.
D. Locate pipe to be analyzed
- 1. On composite drawings
- 2. In the field (if installed)
- 3. If not installed, good idea to see the area anyway to determine de-sireable support locations and potential interferences.
E. Locate axial restraints where required per Section 5.2.
- 1. Runs longer than one span.
- 2. Runs containing concentrated weights.
F. Locate seismic supports, observing span rule's in 5.2 and applicable appendicies.
G. Adjust as required for thermal and/or seismic anchor movement (SAM) per Section 5.3.
- 1. Cases 1 thru 4 rely on the engineer being able to prove similarity between his piping configuration and support layout and one of the cases.
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- 2. Case 5 concerned with thermal acceptance of expansion loops.
- 3. Case 6 deals with end displacement and associated limiting spans and resultant loads.
- 4. Case 7 evaluates stresses and loads associated with relative dis-placement between anchors.
H. Place any required valve operator supports per Section 5.2.7 and Appendix A-4.3.
I. Detennine support and nozzle loads per applicable Sections 5.1.2 and 5.2 and Appendicies A thru E.
J. Sunnarize support and nozzle loads on respective load summary sheets.
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(IL SSER ACT-?3 11/2/84 SSER 1.
Allegation Group: Mechanical and Piping Category 40 2.
Allegation humber: AQP-23 3.
Characterization:
The Region IV Resident Reactor Inspector (RRI) determined that there was no quality assurance effort being made by the licensee in regard to the Class 5 hangers / supports.
4 Assessment of Safety Significance:
Region IV letter to TUEC June 23 1980 Appendix A, Notice of Violation cited the TUEC failure to implement a quality assurance program and identified the Region IV inspection report (IR) 80-15. Region IV Reactor Construction and Engineering Support Branch letter July 22, 1980 to TUEC requested TUEC to furnish a written reply within 30 days, including:
(1) corrective steps which have been taken by you, and the results achieved;
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(2) corrective steps which will be taken to avoid further noncompliar ce; and (3) the date when full compliance will be achieved.
TUEC letter TXX 3177, August 18, 1980 responded to the Region IV letter as follows:
(1) Corrective Steps Which Have Been Taken and Results Achieved The applicable fabrication and installation specifications have been reviewed and now include specific provisions for Quality Assurance criteria to be applied to the design, fabrication and installation of Class 5 Hangers. Construction and Quality Control procedures to incorporate these provisions have been prepared and are currently being implemented.
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. (2) Corrective Steps Which Will Be Taten to Avoid further Nonconpliance The stated corrective action will preclude recurrence of the noncompliance.
(3) Date of Full Compliance Implementing procedures,Jere established by July 25, 1980 and are 1
currently being applied to ongoing fabrication and installation activities.
Inspection c' hangers previously installed will be accomplished as soon as practical, consistent with the project schedule for turnover to startup personnel.
l The TRT staff reviewed fabrication and installation specifications and verified that the documents were revised to include Quality Assurance Progran requirements, that the requirements were imposed on suppliers, and that the requirements were implemented on site for the CP construction activity.
Gibbs & Hill (G&H) specification 2323-MS-46B entitled "Non Nuclear Pipe Hangers and Supports" was revised by the issue of design change authorization (DCA) 7955 Rev.1 approved August 19, 1980, to clarify and formalize the program regarding Class 5 pipe supports that have Seismic Category 11 requirements.
Specification Paragraph 3.5.la was revised and paragraph 3.11h added to specify quality program requirements.
4 10Et let ters CPPI. 0072 & 6072 dated Aunust 11, 198C transmitted the DCA to ITT Grinnell (ITT6) and APS Industries (liPSI) fcr application to items supplied to CP on Purchase Orders CP-0046B, and CP-0540E,.l. The DCA 7455 Rev.1 was incerporated in Rev. 3 of Specificatier l'5-46B.
G&H specification 2323-145-100, " Piping Erection Specification" was revisec by the issue of DCA 7952 approved July 22, 1980.
This DCA revised specification paragraph 7.1.12 and added Appendix B entitled
" Quality Program Requirenents for lion touclear Safety Related Seismic Category 11 Supports." The DCA was incorporated in Revision 6 of the Specification.
TUEC QA periodic audits report on the implementation of QA program requirements by the supplier / vendor. The TRT staff assessment of the TUEC audits is addressed in a later section of this SSER.
TUEC instruction number QI-QP-11.ll-1 entitled " Installation Inspections of Class 5 Pipe Supports" was issued on July 25, 1980 to set forth the criteria and requirements (and a detailed inspection checklist-author) to be used when performing installation inspection cf Class 5 supports. On fiovember 2,1981, QI-QP-11.11-1 was withdrawn fron use and replaced by TUEC instruction number QI-QP-11.16.1 entitled " Installation Inspections
F 5-cf h! 5 Seist,ic Categor,. II Supports fer Class V (5) Piping."
In addition
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tc the inspection criteria detailed in Q:-QP-il.11.-l for installation inspection, the replacement instruction 0;-QP-ll.16.-l added criteria for fabrication inspections and provides additional detail inspection checklists.
The 'RT staff reviewed a random sample censisting of eleven Class 5 Support Record Packages to determine the implementation of QA program requirements as identified in the aforemer.tioned TUEC corrective action reply to Regicr: IV. This review also verified that the inspection of previously installed CL5 supports was accor'plished by an ongoing records verificat an program to assure that there was an inspection report record package for all CLV supports. The verification was perforned by CL5 QA/0C and is documented by use of the inspection report Attachment 17 to QI-QF-ll.16.1. During the review of the eleven packages the TRT observed that the inspection report is included in the support record package.
Support Packages SI-1-035-700-5355R and SFX-040-004-A55R are typical for the eleven support packages reviewed.
This review by the TRT staff included the verification of training and certification records for five QC inspectors that had performed inspections of Class 5 supports in accordance with QI-QP-ll.11-1 and QI-QP-11.16-1. The records covered a time span from. August 15, 1980 through July 12, 1983, and were found to be satisfactory.
. A sample of recciving inspection records, were revie ed by the TRT staff to assure that the receiving inspection activity cc-formed to the requirements of brcwn & Root (B&R) Procedure CP-CPli 8.1 entitled " Receipt Storage and Issuance of items." Material Received Record (MRR) 1282 August 23,1977; 9242 April 22,1981; and 11402 January 10, 1983, for Class 5 supports and materials received from ITT-G contain copies of ITT-G inspection reports, G&H quality control release form, and ITT-G certificates cf ccmpliance that materials and fabrication comply with the applic;ble requirenents of ANSI B31.1, 1973. MRRs for material received from NPSI, 2622 July 6, 1978; 7398 March 21, 1980; 11422 February 14, 1983 contain copies on NPSI inspection reports and certificates of compliance indicating compliance with TUGC0 Purchase Order 0046 B.1, ANSI-B31.1 and specification MS465. It is significant to the TRT staff that prior to the imposition of quality progran requirements (circa July 25, 1980) the two suppliers had provided evidence in the form of inspection reports and certification of conformance to quality requirements.
This evidence will assist the TRT staff conclusion in regard to safety significance.
I
Supplicr Audits in an interview with the TUEC Supervisor, OA Audits, and the TUEC Site QA Manager; TUEC personnel explained that the TUEC QA system cf supplier / vendor audits is enhanced by quality assurance source inspections of material at supplier locations and a vendor rating system.
After initial evaluation and approval periodic audits were performed.
When source inspection results and the vendor rating system indicated the need for improved quality performance by the supplier then TUEC i
QA performed additional audits and surveillances to assure that the supplier quality performance was restored to an acceptable level.
TUEC QA Audits Supervisor and Site QA Manager explained that the CL5 supports suppliers were on the TUEC approved vendors list with an approved QA program prior to the imposition of quality program requirements for CL5 supports and that the suppliers quality performance was satisfactor. Based on the satisfactory performance
/
TUEC did not deem it necessary to perforn a supplier evaluation nor a QA audit discrete to quality program requirements for CL5 supports. The TUEC QA Audits Supervisor further explained that all audits of ITT-G and NPSI reported on the suppliers quality program performance in accordance with 10 CFR 50 Appendix B.
i
. Although TUEC QA personnci did not provide clear iccntification of tht IT1-G and NPSI approved quality programs for purchase ordcrs 0046B anc 0046B.1, the TRT review of the TUEC QA supplier evaluations and audit reports affirmed that QA supplier evaluation anc QA audits and surveillances were performed. The TRT reviewed TUEC QA records of vendor audits of ITTG and NPSI for the years 1981 thru 1984.
This audit and surveillance activity was in conformance with TUEC QA Procedure DQP-CS-2 The TUEC QA program is committed to ANSI N45.2.12-1973, " Requirements for Auditing of QA Programs for Nuclear Power Plants." Section 3.4 Scheduling subparagraph 3.4.2 states: " Audits shall be regularly scheduled on the basis of the status and safety impdttance of the activities to assure conformance with the developed and implemented program. Applicable elements of the quality assurance program shall be audited at least annually or at least once within the life of the activity whichever is shorter." The TRT found that annual audits of ITT-G and NPSI locations were not performed for the Class 5 supports procurements. ANSI N45.2.12 paragraph 3.4.3 subparagraph 3.4.3.3 states: " Supplemental audits are conducted when significant changes are made in functional areas of the QA progran such.as significant reorganization or procedure revisions."
Although not a reorganization or a procedure revision, that TRT regards it significant that QA program requirements were imposed on the two suppliers in August 1980 by revision to Specificat. ion MS-0046B, (DCA 7955). The TRT did not find evidence of a TUEC QA supplemental audit of ITT-G and NPSI to determine the implementation of the newly imposed quality program.
9 Thc TUEC Procedurc DQP-CS-4 subpara. 3.2.3 states Ir lieu of regularly schedulec audits of ver. dors TUGC0 QA will perform the following: Monitor the individual vender ratings.... if an adverst trend is evident an audit will be scheduled." The TRT finds that this is centrary tc ANSI N45.2.12 which requires regularly scheduled audits of vendors.
Therefore the TUEC procedure does not conform to the ANSI requirements.
Internal Audits The TRT staff reviewed TUEC audit records to deterrine that a system of planned and scheduled periodic audits was implemented to determine the effectiveness of the quality program requirements applicable to Class 5 supports.
TUEC DQP-CS-4 " Procedure to establish and apply a system of pre-award evaluations, audits and surveillance;" and the TUEC proposed audit schedule (for) internal and prime subcontractor (audits on site) for years 1982 and 1984 were included in the review. Results of the review are as follows:
1.
TUEC QA surveillance of Class 5 pipe support activity per TUEC instruction QI-QP-ll.16-1 was reported in TUEC site surveillance report SSR 163. The surveillance was performed December 2-9, 1981.
The TRT staff notes that this surveillance was performed within a short time after issue of the instruction on November 2, 1981.
.. 2.
The TUEC audit status for year 1982, - Audit of construction /QC Class V scheduled hovenber 29 - December 3, 1902, indicates that the audit was not performed.
TUEC status mero QTQ-264 January 1, 19E3, i
states: "This activity has been reviewed during mechanical audits during 1982.
The status report shows that audit TCP-39 performed April 19-23, 1982 audited Constructier./QC - AS E mechanical / piping and supports.
i i
3.
TUEC QA audit TCP 76 June 26 - July 1,1983, covered Construction /QC nerhanical:
non ASME.
This audit covered installation inspections of NNS seismic Category 11 supports for Class 5 piping in accordance with instruction QI-QP-ll.16-1 4.
The TUEC QA preposed audit schedule Rev. 1 for year 1984 does not provide for a scheduled internal and prime subcontract audit discrete to construction activity for Class 5 pipe supports. TUEC reason for the revised audit schedule is stated in TUEC office memorandum QTQ 695 dated May 15, 1964 as follows:
11 "This revision te the original Audit Plan for 1904 has been developed tr. raore adequately accenplish audit goals during the ccepletion of Unit 1 construction and startup testing and to assure proper audit activity of Unit 2 construction during this period.
Also, the Operations audit plans have been revised based ore an ar.ticipated September fuel load date. This revision incorporates the changes we discussed on May 7, 1984."
The revised audit schedule for year 1984 deletes the subcontracter/ prime audit of Grinnell site activity which was originally scheduled for the first quarter of 1984.
Foot note 4 in the audit schedule states:
" Cancelled, no current activity; will be rescheduled when Unit 2 work is in process. The TRT finds that there is no item of concern with the 1984 schedule.
5.
Conclusion and Staff Positions:
Since the violation was reported in Region IV IR 80-15 and TUEC responded to the Region IV request for corrective action the TRT staff agrees that the violation is substantiated.
l 4
- 1T -
Io its asscstr+nt of safct 3 s ignif ic e nc e, for t u vi; lat iu, the TFT s t af f reviewed spec if icat ions, procedures, inst ructicr.s, receiving and sitt audits.
j insrcction records QC inspcction records and 0A sm; 'ier This review deterrined that TUEC, in response to th( Region IV request for l
5 implemented quality progi am requirements for C ass correctivc action, pipe su;morts. Besed cr. the assessnent the TRT staff concludes that l1 therc is no saf ety significance nor generic implication.
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0" TU TUEC shall review and revise procedure DQP-CS-4 to provide for the implementation of regularly scheduled audits, of v.ndors in conformance with the ANSI N45.2.12.
v i
. Procedure DQP-CS-4 current Rev. 10 is not clear in its intert to cever the operations phase if CP Unit 1 and the constructior, phase for Unit 2.
As currently written it is confusing.
b b
-/
RT recommends that UEC prepare the procedure in two sections e.g. construction / operations or consider a separate procedure for operations.
8.
Attachments: None 1
9.
Reference Documents:
1.
Design Change Authorization 7952 and 7955-Rl.
2.
Training and Certification Records for QC Inspectors:
J. McClain, R.D. Smith, J. Leigh, M. Hamburg, D. McCallum.
3.
Material received record 1282 9242 11403 2622 7398 11422.
4.
Class 5 Support QA Record Package SI-0-035-700-535R and SFX-040-004-055R Typical for Eleven Support Packages reviewed.
5.
TUEC QA Audit Plan and Schedule - Internal and Prime Subcontractor for years 1982, 1983, and 1984.
6.
TUEC QA Audit Plan for Audit No. TGF-4.
7.
TUEC QA Construction Site Surveillance Report No. 81-1 6.
p y
--u-
. 8.
TUEC QA Audit f.o. TCP-76 Audit Summary.
9.
TUEC Letters TXX 3165, TXX 3177, CPPA 6072, CPPA 6073.
- 10. Audit Records ITT-G Warren - ITT-3, and 7; Audit Records ITT-G Providence ITT-4, 8, and 10.
- 11. Audit Records NPSI-Portlar.d TNP-2,
-4, and -6; Audit Reccrds NPSI-Secaucus TUP-5,-9, and -11; Audit Records NSPI-Austin TNP-1,
-3,
-7,
-8, and -10.
- 12. Region IV Inspection Repot 80-15.
- 13. G&H Specification 2323-P.5-46B - Non-Nuclear Pipe Hanger and Supports.
- 14. G&H Specification 2323-tis-100 - Piping Erection Specificatior..
- 15. TUEC Procedure DQP-CS-4 Procedure to Establish and Apply a System of Preaward Evaluations Audits and Surveillances.
- 16. TUEC Instruction QI-QP-11.11-1 Installation Inspections of Class 5 Pipe Supports.
- 17. TUEC Instruction QI-QP-11.16-1 Installation Inspections of NHS Seismic Category II Supports for Class 5 piping.
- 18. B&R Procedure CP-CPM-8.1 Receipt Storage and Issuance of Itens.
- 19. FSAR Table 17 A-1,
- 20. TUEC Procedure CP-QP-11-16 Inspection of Seismic Category II Supports and Structural Steel.
- 21. ANSI N45.2.12 Draft 3, Rev. O dated May 2, 1973.
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- 10. This statement prepared by:
J. H. Malonson Name Date f
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Reviewed by:
L. C. Shao Date i
Group Leader 1
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Approved by:
4 i
t V. Noonan Date 4
Project Director 4
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Writeup Violations to Region Potential Workpackage File Complete _____,,________Workpackage R FolA-85-59 dd-a//
i DCP5 - SSER AQP-23 12/7/84 Draft 4 SS.ER
. yo i
llechanical and Piping Category 40 1.
Allegation Group:
2.
Allegation Number: AQP-23 The NRC Region IV (RIV) Resident Reactor Inspector Characterization:
3.
by (RRI) determined that there was no quality assurance effort bein the licensee in regard to the Class 5 hangers / supports.
An RIV letter to Texas utilities Assessment of Safety Significance:
4.
23, 1980, " Appendix A, Notice of Electric Company (TUEC) dated June Violation," based on RIV inspection report (IR) 80-15, cited the TU A second letter from failure to implement a quality assurance program.
RIV's Reactor Construction and Engineering Support Branch, da 1980, requested TUEC to furnish a written reply within 30 days, including:
corrective steps which have been taken by you, and the (1) results achieved; corrective steps which will be taken to avoid further 1
(2) noncompliance; and the date when full ccmpliance will be achieved.
(3)
I l
- - =
s 7
I
' +
1 TUEC responded by letter.(TXX 3177), dated August 18, 1980, to RIV as a
follows:
(1) Corrective Steps Which Have Been Taken and Results Achieved 4
The applicable fabrication and installation specifications have j
been reviewed and now include specific provisions for Quality i
Assurance criteria to be applied to the design, fabrication,
^
and installation of Class 5 hangers. Construction and Quality
)
Control procedures to incorporate these provisions have been i
prepared and are currently being implemented.
I P
(2) 4 Corrective Steps Which Will Be Taken to Avoid Further Noncompliance The stated corrective action will preclude recurrence of the noncompliance.
d (3) Date of Full Compliance Implementing procedures were established by July 25, 1980, and j
are currently being applied to ongoing fabrication and installation activities.
Inspection of hangers previously installed will be accomplished as soon as practical, consistent with the p,roject schedule for turnover to startup personnel.
l 1
,.m.
4
'=R'
. The NRC Technica.1 Review Team (TRT) reviewed fabrication and installation specifications and verified that the documents were revised to include quality assurance program requirements, that the requirements were imposed on suppliers, and that the requirements were implemented on site for the Comanche Peak Steam Electric Station (CPSES) construction activity.
The TRT found that Gibbs & Hill (G&H) specification 2323-MS-46B, "Non-Nuclear Pipe Hangers and Supports," was revised by the issue of design change authorization (DCA) 7955, Rev. 1.
This revision, which was approved on August 19, 1980, clarified and formalized the program regarding Class 5 pipe supports having Seismic Category II requirements.
f;fKHdA7.Or,/- "t:'/,gparagraph 3.5.la was revised and paragraph 3 to specify quality program requirements.
The TRT determined that TUEC let?.ers CPPA 6072 and 6073, dated August 11, 1980, transmitted DCA 7455 to ITT Grinnell (ITTG) and NPS Industries
.l tlJ "-
(NPSI) for application to items supplied to CPSES on purchase orders DCA'Y45[Rev.1, was also incorporated lu/J CP-0046B and CP-0046B.l.
e w._
Rev. 3 of specification MS-46B. Periodic TUEC QA audits also reporttd on the implementation of QA program requirements by the supplier /v6ador.
The TRT staff assessment of the TUEC audits is addressed in a later section of this SSER.
i
. The TRT found that G&H specification 2323-MS-100, " Piping Erection Specification," was revised by the issue of DCA 7952, which was approved on July 22, 1980. This DCA revised specification paragraph 7.1.12 and added Appendix B, " Quality Program Requirements for Non Nuclear Safety Related Seismic Category II Supports." The DCA was then incorporated W
h Rev. 6 of specification 2323-MS-100.
TUEC. instruction number QI-QP-il.ll-1, " Installation Inspections of Class 5 Pipe Supports," was issued on July 25, 1980, to set forth the criteria and requirements and to provide a detailed inspection checklist to be used when performing installation inspection of Class 5 supports.
On November 2, 1981, QI-QP-ll.ll-1 was withdrawn from use and replaced by TUEC instruction number QI-QP-11.16.1, " Installation Inspections of Nh5 Seismic Category II Supports for Class V (5) Piping."
In addition to the installation inspection criteria detailed in QI-QP-ll.ll.-1, replacement instruction QI-QP-11.16.-l added criteria for fabrication inspections and provided additional detailed inspection checklists.
The TRT staff reviewed a random sample of 11 Class 5 (CL5) Support Record Packages to determine the implementation of QA program requirements as identified in TUEC's corrective action response to RIV. This review verified that the inspection of previously installed CL5 supports was accenplished by an ongoing records verification program to assure that there was an inspection report record package for all CL5 supports. The
^
. verification was performed by CL5 QA/QC and was documented by inspection report Attachment 17 to QI-QP-11.16.1. During the review of the 11 packages, the TRT observed that the inspection report was included in each of the support record packages.
The review by the TRT staff also included the verification of training and certification records for the five QC inspectors who had performed inspections of CL5 supports in accordance with QI-0P-ll.11-1 and QI-QP-11.16-1. The records covered a time span from August 15, 1980, through July 12, 1983. The TRT found these records to be satisfactory.
The TRT also reviewed a sample of receiving inspection records to ensure that the receiving inspection activity conformed to the requirements of Brown & Root (B&R) Procedure CP-CPM 8.1, " Receipt, Storage, and Issuance of Itens." Material received records (MRRs) (MRR-1282, dated August 23, 1977; -9242, dated April 22, 1981; and -11403, dated January 10, 1983),
which were for Class 5 supports and materials received from ITTG, contained copies of ITTG inspection reports, a G&H quality control release form, and ITTG certificates of compliance showing that materials and fabrication complied with the applicable requirements of ANSI B31.1, i
1973. MRRs for material received from NPSI, (MRR-2622, dated July 6, 1978; -7398, dated March 21, 1980; -11422, dated February 14, 1983) contained copies of NPSI inspection reports and certificates of cenpliance indicating compliance with TUEC purchase order 0046 B.1, ANSI-B31.1 and specification MS46B. Significantly, the TRT found that prior to imposing quality program requirements (circa July 25,1980),
. the two suppliers had provided evidence in the form of inspection reports and certification of conformance to quality requirements.
In a TRT interview with the TUEC Supervisor of QA Audits ;'id the TUEC Site QA Manager, these personnel explained that the TUEC QA system of supplier / vendor audits was enhanced by quality assurance source inspections of material at supplier locations and by a vendor rating system. The TRT learned that after initial evaluation and approval, periodic audits were performed. When the source inspection results and the vendor rating system indicated the need for improved quality performance by the supplier, TUEC QA performed additional audits and surveillances to assure that the supplier's quality performance was restored to an acceptable level.
The TUEC QA Audits Supervisor and Site QA Manager explained that the CL5 supports suppliers were on the TUEC approved venders list and had an approved QA progran prior to the imposition of quality program requirements for CL5 supports. They also stated that the suppliers
~
quality performance was satisfactory. Based on this satisfactory performance by its vendors, TUEC did not deem it necessary to perform a supplier evaluation nor a QA audit for quality program requirements for CL5 supports. The TUEC QA Audits Supervisor further explained that all ITTG and NPSI audits were reported based on the supplier's quality program performance in accordance with 10 CFR 50 Appendix B.
. Although TUEC QA personnel did not provide clear identification of the ITTG and NPSI. approved quality programs for purchase orders 0046B and 0046B.1, the TRT review of the TUEC QA supplier evaluations and audit reports affirmed that QA supplier evaluations, as well as QA audits and surveillances, were performed. The TRT reviewed TUEC QA records of vendor audits of ITTG and NPSI for the years 1981 through 1984, and found that this audit and surveillance activity was in conformance with TUEC QA Procedure DQP-CS-4.
The TUEC OA program is committed to ANSI N45.2.12-1973, " Requirements for Auditing of QA Programs for Nuclear Power Plants." Section 3.4,
" Scheduling," subparagraph 3.4.2 states: " Audits shall be regularly scheduled on the basis of the status and safety importance of the 4
activities to assure conformance with the developed and implemented program. Applicable elements of the quality assurance program shall be auditeo at least annually or at least once within the life of the activity, whichever is shorter." The TRT found that annual audits of ITTG and NPSI locations were not performed for the Class 5 supports procurements.
ANSI N45.2.12, paragraph 3.4.3, subparagraph 3.4.3.3, states:
" Supplemental audits are conducted when significant changes are made in functional areas of the QA program, such as significant reorganization or procedure revisions." Although they were not reorganization or procedure revisions, the TRT regards it as significant that Qh progran requirements were imposed on the two suppliers by revision to specification MS-0046B l
h /
(DCA 7955) in August 1980. The TRT found no evidence that TUEC made a supplemental QA audit of ITTG and NPSI to determine the inplementation of J -
the newly imposed quality program.
J
-A p&
%f,k TUEC Procedure DQP-CS-4, subpara. 3.2.3, states: "In lieu of regularly
/
scheduled audits of vendors,TUGC0 QA will perform the fol
- Monitor theindividualvendorratings....'fThe[pr J e fe s3 ' 41f an f
~-
-J adverse trend is evident an audit will be scheduled." The TRT determined that this procedure is contrary to ANSI N45.2.12, which requires regularly. scheduled audits of vendors.and dn~
c;c re.., w J.a "ZI F
.R.
urJ r W The TRT reviewed TUEC's audit records to deternire if a system of planned and scheduled periodic audits was implencnted to determine the effectiveness of the quality program requirements applicable to CL5 supports. TUEC DQP-CS-4, " Procedure to Establish and Apply a System of Preaward Evaluations, Audits and Surveillance," and the TUEC proposed audit schedule for internal and prime subcontractor audits onsite for the rMd years 1982 med 1984, were included in the review.
The results of the TRT review were as follows:
1.
TUEC QA surveillance of CL5 pipe support activity (per TUEC instruction QI-QP-11.16-1) was reported in TUEC site surveillance report SSR 163. The surveillance was performed December 2-9, 1981. The TRT noted that this surveillance was performed within a short time after issuance of the instruction on November 2, 1981.
_g_
2.
The TUEC audit status for year 1982, " Audit of Construction /QC Class 5 Scheduled November 29 - December 3, 1982," indicates that the audit was not performed. TUEC status memo QTQ-264, dated January 1, 1983, states:
"This activity has been reviewed during mechanical audits during 1982." The status report showed that audit TCP-39, performed April 19-23, 1982, audited Construction /QC, ASME mechanical / piping and supports.
3.
TUEC QA audit TCP 76, June 26 - July 1, 1983, audited Construction /QCp sechanical. p s*SME, y
This audit covered installation inspections of non-nuclear safety (NNS) seismic Category II supports for CL5 piping in accordance with instruction QI-QP-11.16-1.
4.
TUEC's proposed QA audit schedule, Rev. 1, for year 1984, did not provide for a scheduled internal and prime subcontract audit discrete to construction activity for CL5 pipe supports.
TUEC's eason for the revised audit schedule was stated in TUEC office memorandun QTQ 695, dated May 15, 1984, as follows:
A)s r]r
("This revision to the original Audit Plan for 1984 h developed to more adcouately accomplish audit goals during the completion of Unit 1 construction and startup testing and to assure proper audit activity of Unit 2 construction during this
I e :
period. -Also, the Operations audit plans have been revised based on an anticipated September fuel-load date. This revision incorporates the changes we discus:ed on May 7, 1984."
p i
i
, The revised audit schedule for year 1984 deletes the subcontractor / prime j
audit of ITTG site activity, which was originally scheduled for the first quarter of 1984. Footncte 4 in the audit schedule states: " Cancelled, no current activity; will be rescheduled when Unit 2 work is in process."
The TRT cercurred that there is ac ced t; a J;; ITTC o,n.il,m,k un U,, ; ;
l
- m sur.
F-suc5 T'as~~
THC4A e% iso I ^ *?m a c - (C /JC rwJ W ' TH-mal i9 B'/ 3 c JC >t 0.
I 5.
Conclusion and Staff Positions: Since the violation was reported in RIV's IR 80-15 and TUEC responded to the RIV request for corrective action, the TRT agrees that this violation is substantiated.
In its assessment of safety significance for the violation, the TRT reviewed specifications, procedures, instructions, receiving inspection records, QC inspection records, and QA supplier and site audits. This review determined that in response to the RIV request for corrective action, TUEC implemented quality program requirements for CL5 pipe
- upport:. 5:cd cr. thi: s:scs: cent, the TRT concludes that this allegation has neither safety significance nor generic implication.
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Reference Documents:
1 1.
Design Change Authorization 7952 and 7955-Rl.
2.
Training and Certification Records for QC Inspectors:
J. McClain, R.D. Smith, J. Leigh, M. Hamburg, D. McCallum.
I 3.
Material received records 1282, 9242, 11403, 2622, 7398, and 11422.
4.
Class 5 Support QA Record Package SI-0-035-700-535R and SFX-040-004-055R (typical for 11 support packages reviewed).
5.
TUEC-QA Audit Plan and Schedule - Internal and Prime Subcontractor for years 1982, 1983, and 1984.
6.
TUEC QA Audit Plan for Audit No. TGF-4.
7.
TUEC QA Construction Site Surveillance Report No.81-163.
8.
TUEC QA Audit No. TCP-76 Audit Summary.
9.
TUEC Letters TXX 3165, TXX 3177, CPPA 6072, and CPPA 6073.
- 10. Audit Records ITTG Warren - ITT-3, and 7; Audit Records ITTG Providence ITT-4, 8, ar.d 10.
- 11. Audit Records NPSI-Portland TNP-2,
-4, and -6; Audit Records NPSI-Secaucus TNP-5,-9, and -11; Audit Records NPSI-Austin TNP-1,
-3,
-7,
-8, and -10.
- 12. Region IV Inspection Repot 80-15.
i
- 13. G&H Specification 2323-MS-46B, "Non-Nuclear Pipe Hanger and Supports."
- 14. G&H Specification 2323-MS-100, " Piping Erection Specification."
- 15. TUEC Procedure DQP-CS-4, " Procedure to Establish and Apply a System of Preaward Evaluations Audits and Surveillances."
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- 16. TUEC Instruction QI-QP-11.ll-1, " Installation Inspections of Class 5 Pipe Supports."
- 17. TUEC Instruction QI-QP-ll.16-1, " Installation Inspections of NHS Seismic Category II Supports for Class 5 Piping."
- 18. B&R Procedure CP-CPM-8.1, " Receipt Storage and Issuance of Items."
- 19. FSAR Table 17 A-1.
TUECProcedureCP-QP-il-16,"InspectionofSdismic(ftegoryII 20.
Supports and Structural Steel."
- 21. ANSI N45.2.12 Draft 3, Rev. O, dated May 2, 1973.
- 10. This statement prepared by:
J. Malonsen, Date TRT Technical Reviewer Reviewed by:
L. Shao, Date Group Leader Approved by:
V. Noonan, Date Project Director
./
DCPS - SSER AQP-23 Draft 7 -- 3/12/85 6
t SSER 1.
Allegation Group: Mechanical and Piping Category 40 Lack of a QA Program for Class 5 Supports 2.
Allegation Number: AQP-23 3.
Characterization:
The NRC Region IV (RIV) Inspection Report (IR) 80-15 which covered RIV inspections performed in June 1980 reported that there was no quality assurance effort being made by the licensee [ Texas Utilities Generating Company (TUGCO)] in regard to Class 5 hangers and supports. The IR also states: FSAR, paragraph 3.2.2.3 defines Class 5 piping systems as those in the non-nuclear safety category whose failure in a seismic event could result in a loss of capability of a safety-related function.
4.
Assessment of Safety Significance: The TRT found that RIV issued a notice of violation to TUGC0 by a letter dated June 23, 1980 which requested that TUGC0 furnish a written statement or explanation in re;.
i n ' n'i c the details of the corrective action implemented by TUGCO.
The TRT found that Texas Utilities Generating Company (TUEC/TUGCO) responded to the notice of violation and the RIV request for corrective action by a letter TXX-3177 dated August 18, 1980. This letter stated that the applicable Gibbs & Hill (G&H) design and piping erection Specifications were revised and that construction and quality control F0lA-85-59 procedures were prepared and implemented.
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' The TUEC Letter (TXX-3177) also states that:
Impler.enting procedures were established by July 25, 1980 and are currently being applied to ongoing fabrication and installation activities.
Inc.pection of hangers previously installed will be accomplished as soon as practical, consistent with the project schedule for turnover to startup personnel.
The NRC Technical Review Team (TRT) reviewed design, fabrication, and installation specifications and verified that these documents were revised to include quality assurance program requirements, for Class 5 supports, that the requirements were imposed on suppliers, and that the requirements were inplemented on site for the Ca.anche Peak Steam i
Electric Station (CPSES) construction activity.
The TRT found that Gibbs & Hill (G&H) specification 2323-MS-46B, "Non-Nuclear Pipe Hangers and Supports," was revised by the issue of design change authorization (DCA) 7955, Rev. 1.
This revision, which was approved on August 19, 1980, clarified and ferneltzec the program regarding Class 5 pipe supports having Seisuit (etegorj II requirements.
Specification paragraph 3.5.la was revised and paragraph 3.11h was added to specify quality program requirements.
The TRT determined that TUEC letters CPPA 6072 and 6073, dated August 11, 1980, transmitted DCA 7955 to ITT Grinnell (ITTG) and NPS Industries (NPSI)forapplicationtoitemssuppliedtoCPSESonpurchaseorders CP-0046B and CP-00468.1. OCA 7955, Rev. 1, was incorporated in Rev. 3 of
\\
specification MS-46B.
_ -- ~ _.
. The TRT found that G&H specification 2323-MS-100, " Piping Erection Specification," was revista by the issue of DCA 7952, which was approved on July 22, 1980, lhtt DCA revised specification paragraph 7.1.12 and added Appendix B, " Quality Program Requirements for Non Nuclear Safety Related Seismic Category II Supports." The DCA was incorporated in Rev.
1 6 of specification 2323-f:5-100.
TUEC instruction number Ql-QP-11.11-1, " Installation Inspections of j
Class 5 Pipe Supports," was issued on July 25, 1980, to set forth the criteria and requ:ier.ents eiic tc provide a detailed inspection checklist to be used when performing installation inspection of Class 5 supports.
l On November 2, 1981, QI-QP-11.11-1 was withdrawn from use and replaced by l
TUEC instruction number QI-QP-11.16.1, " Installation Inspections of NNS Seismic Category II Supports for Class V (5) Piping."
In addition to the installation inspection criteria detailed in QI-QP-11.11.-1, replacement instructior. 01-0P-11.10.-1 added criteria for fabrication 4
inspections ar.c providcc tteitional detailed inspection checklists.
The TRT staff reviewed a random sample of 11 Class 5 Support Record Packages to determine the implementation of QA program requirements as identified in TUEC's corrective action response to RIV. This review verified that the inspection of previously installed Class 5 supports was accomplished by an ongoing records verification program to assure that there was an inspection report record package for all Class 5 supports.
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. l The verification was performed by Class 5 QA/QC and was documented by inspection report Attachment 17 to QI-QP-11.16-1. During the review of the 11 packages, the TRT observed that the inspection report was included in each of the support record packages. This review by the TRT staff also included the training and certification records for the five QC inspectors who had performed inspections of Class 5 supports in accor-dance with QI-QP-11.11-1 and QI-QP-11.16-1. The records covered a time span from August 15, 1980, through July 12, 1983. The TRT found these records to be satisfactory.
f The TRT also reviewed a sample of receiving inspection records to ensure 4
that the receiving inspection activity conformed to the requirements of Erown & Root (B&R) Procedure CP-CPM 8.1, " Receipt, Storage, and Issuance of Items." Material received records (MRRs) (MRR-1282, dated August 23, 1977; -9242, dated April 22, 1981; and -11403, dated January 10,1983),
which were for Class 5 supports and materials received from ITTG, contained copies of ITTG inspection reports, a G&H quality control release form, and ITTG certificates of compliance showing that materials and fabrication
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v ith the applicable requirements of ANSI B31.1,1973. MRRs for material received from NPSI, (MRR-2622, dated July 6, 1978; -7398, dated i
March 21, 1980; -11422, dated February 14,1983) contained copies of NPSI inspection reports and certificates of compliance indicating compliance i
with TUEC purchase order 0046 B.1, ANSI-B31.1 and specification MS46B.
The TRT found that prior to TUEC's imposing the quality program require-ments on ITT-G and NPSI (August 11,1980), the two suppliers had provided evidence of compliance with quality program requirements in the form of inspection reports and certificates of conformance.
. The TRT intervicwed the TUEC Supervisor of QA audits and the TUEC Site QA Manager and reviewed the TUEC QA records for the audits of ITT-G, NPSI and the site (CPSES). The interview and review were performed by the TRT to determine that the quality program, for Class 5 supports, was effectively implemented (as of July 25,1980) in accordance with TUEC's response to the RIV Notice of Violation. The TUEC QA Audits Supervisor and Site QA Manager explained that the Class 5 supports suppliers (ITT-G and NPSI) were on the TUEC approved vendors list and had a TUEC approved QA program prior to the imposition of the quality program requirements for Class 5 supports (August 1980). They also stated that the suppliers' quality performance were satisfactory. Based on this satisfactory performance by its vendors TUEC did not deem it necessary to perform a supplier evaluation nor a QA audit of the suppliers' quality program for Class 5 supports at that time. The TUEC QA Audits Supervisor further explained that all ITT-G and NPSI audits were reported based on the supplier's quality program performance in compliance with 10 CFR 50 Appendix B.
Although TUEC QA personnel did not provide clear identification of the ITTG and NPSI approved quality programs for purchase orders 0046B and 0046B.1, (for the Class 5 supports) the TRT review of the TUEC QA supplier evaluations and audit reports affirmed that QA supplier evaluations, as well as QA audits and surveillances, were performed by TUEC. The TRT reviewed TUEC QA records of vendor audits of ITT-G and NPSI for the years 1981 through 1984, and found that this audit and
. surveillance activity was in conformance with TUEC QA Procedure DQP-C5-4, procedure to establish and apply a system of preaward evaluations, audits and surveillances.
The TUEC QA program is committed to ANSI N45.2.12-1973, " Requirements for Auditing of QA Programs for Nuclear Power Plants." Section 3.4, "Schedul-ing," subparagraph 3.4.2 states: " Audits shall be regularly scheduled on the basis of the status and safety importance of the activities to assure conformance with the developed and implemented program. Applicable elements of the quality assurance program shall be audited at least annually or at least once within the life of the activity, whichever is shorter." The TRT found that contrary to the ANSI requirement, QA program audits, of ITT-G and NPSI for the procurement of Class 5 supports, were not performed on a regularly scheduled basis, or at least annually.
The TRT also found that TUEC Procedure DQP-CS-4, subpara. 3.2.3, states:
"In lieu of regularly scheduled audits of vendors TUGC0 QA will perform the following: Monitor the individual vendor ratings..."
...if an adverse trend is evident an audit will be scheduled." The TRT founu tL '
this procedure is contrary to ANSI N45.2.12, which requires regularly scheduled audits of vendors.
ANSI N45.2.12, paragraph 3.4.3, subparagraph 3.4.3.3, states: " Supplemental audits are conducted when significant changes are made in functional areas of the QA program, such as significant reorganization or procedure revisions." Although they were not reorganization or procedure revisions, the TRT regards it as significant that QA program requirements were 1
imposed on the two suppliers by revision to specification MS-0046B (DCA 7955, Rev. 1) in August 1980. The TRT found no evidence that TUEC performed a supplemental QA audit of ITTG and NPSI to determine the implementation of the newly imposed quality progran for Class 5 supports.
The TRT reviewed TUEC's QA internal (site) audit schedule and status records to determine if a system of planned and scheduled periodic audits was implemented to determine the effectiveness of the quality program requirements applicable to site activity for the fabrication, installation and inspection of Class 5 supports. The TRT found that regularly scheduled QA audits of the Class 5 supports (site) activity were not performed in 1981 and 1982. The TRT alse #tund that at cedit (TCP-76) was performed on schedule in June-July 1983, however, an audit was not scheduled for 1984, due to (as stated in the TUEC QA Revised Audit Plan) startup testing in Unit 1 and revised operations audit plans based on an anticipated September 1984 fuel load date. Since there was no audit scheduled and performed in the year 1981, and the scheduled audit was not performed in 1982, the TRT found this to be in violation of the ANSI N45.2.12 which requires the performance c' 1 r;-
1 c:5tduled periodic audits.
The TRT noted that the NRC construction appraisal team (CAT) report,Section VIII quality assurance, concluded that weaknesses in TUEC's established audit program included the scheduling and frequency of audits. The TRT also noted that QA audits are addressed in QA/QC Category 7, AQ-ll3 and AP-132.
. i 5.
Conclusion and Staff Positions: Since the violation was reported in RIV's IR 80-15 and.TUEC responded to the RIV request for corrective action, the TRT agrees that this violation is-substantiated.
In its assessment of safety significance for the violation, the TRT reviewed specifications, procedures, instructions, receiving inspection records, QC inspection records, and QA supplier and site audit records.
This review determined that in response to the RIV request for corrective action, TUEC implemented quality program requirements for Class 5 pipe supports. Although this assessment found potential violations in the TUEC QA program audits systen, the TRT concludes that there is no safety significance nor generic implication.
6.
Actions Required: The TRT suggested that TUEC QA provide record documentation which identifies the vendor (ITT-G and NPSI) QA programs applicable to each supplier location where work is performed under TUEC purchase crders 0046B and 0046B.l.
Procedure DQP-CS-4 current i.v: 1C ir r.c. . ear in its intent to cover the operatione phase for CPSES Unit 1 and the construction phase for Unit 2.
TRT recor. tends that TUEC prepare the procedure in two sections, e.g.,
construction / operations or consider a separate procedure for operations.
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Reference Documents:
1.
Design Change Authorization 7952 and 7955-RI.
2.
Training and Certification Records for QC Inspectors:
J. McClain, R.D. Smith, J. Leigh, M. Hamburg, D. McCallum.
3.
Material received records 1282, 9242, 11403, 2622, 7398, and 11422.
4.
Class 5 Support QA Record Package SI-0-035-700-535R and SFX-040-004-055R (typical for 11 support packages reviewed).
5.
TUEC QA Audit Plan and Schedule - Internal and Prime Subcontractor for years 1982, 1983, and 1984.
6.
TUEC QA Audit Plan for Audit No. TGF-4.
7.
TUEC QA Construction Site Surveillance Report No.81-163.
8.
TUEC QA Audit No. TCP-76 Audit Summary.
9.
TUEC Letters TXX 3165 TXX 3177, CPPA 6072, and CPPA 6073.
- 10. Audit Records ITTG Warren - ITT-3, and 7; Audit Records ITTG Providence ITT-4, 8, and 10.
- 11. Audit Records NPSI-Portland TNP-2,
-4, and -6; Audit Records NPSI-Secaucus TNP-5,-9, and -11; Audit Records NPSI-Austin TNP-1,
-3,
-7,
-8, and -10.
- 12. Region IV Inspection Repot 80-15.
- 13. G&H Specification 2323-MS-468, "Non-Nuclear Pipe Hanger and Supports."
- 14. G&H Specification 2323-MS-100, " Piping Erection Specification."
- 15. TUEC Procedure DQP-CS-4, " Procedure to Establish and Apply a System of Preaward Evaluations Audits and Surveillances."
- 16. TUEC Instruction QI-QP-11.11-1, " Installation Inspections of Class 5 s
Pipe Supports."
i
- 17. TUEC Instruction QI-QP-11.16-1, " Installation Inspections of NNS Seismic Category 11 Supports for Class 5 Piping."
- 18. B&R Procedure CP-CPM-8.1, " Receipt Storage and Issuance of Items."
- 19. FSAR Table 17 A-1,
- 20. TUEC Procedure CP-QP-11-16, " Inspection of Seismic Category II Supports and Structural Steel."
- 21. ANSI N45.2.12 Draft 3, Rev. O, dated May 2, 1973.
j
- 22. NRC Cat Team Report.
j
- 23. SSER QA/QC Category 7 AQ-113 and AQ-132.
- 10. This statement prepared by:
J. Malonson Date TRT Technical Reviewer Reviewed by:
L. Shao Date
{
Group Leader j
I j
Approved by:
V. Noonan Date Project Director
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t JJ N(SI Kf.5.2.12 - 1973 Caution Kocice - This standard is being
.s.
3 p;cpared or revie:cd and has not been
[{l 4
approved by ANSI.
It is subject to
. 5 revisien or withdrawal before issue.
' \\
6 E.UIT.P':E' SIS FCR AUDITT' C OF 7
OC.I.1TY AsJCR*cE PP.0GridM 70R 8
KUCLEAR POL.En PLN7S 9
1.
INTRODUCIION 10 1.1 Purr, se_, - The purpost of this standard is to provide unifore require =ents 11 and guidance for es tu,blishing and i=plementing a sys ten of internal and 12 cxternal audits of quality assurance progre=s for nuclear power plants.
1.2 goff, - This standard amplifics the requirene n:s of R:SI N45.2, Section 19
(.
and chall be u ed in ::njunction with that r.tandard.' This stand:rd pr= vide:
/_..
requirenants and guidance for the pr.cparation, perforrance, reporting, and 16 follovup_of audits of qualiryysurance-pzogra s for nuclear power plante.-
17 This standard is not applienble to surveillance or inspectf ons for the pur-13 pose of process control or product acceptance. "Titis standard app,lics to 19' both internal and ex Lrnal audits performed by 'or 'for clie plant owner, 20~
centractor'ri,7ndother nizations participating in activities affecting 21 the quality of structurcs, systems, and components which are inportant to 22 the nucicar safety of nuclear power plants.
The activities covered by 23 thic standard include designin;:, purchasing, fabricating, handling, chippin;;,
24 storing, cleaninr,, crecting, installing, inspecting, testing, caintaining,
~
25 repairint', and codifying.
~
26 KOTE:
This standard docs not cover requirements for auditing of plant 27 operationn n'id refueling. These are intended to be covered by 7e n;SI 1118.7 - 1972.
-as a e.
FUlA-5-59
==
r Draft 3, Rev. 0 s
j May 2, in73 CC
.317
_ ~. _
' f'
(
l.3 nc nnennihiliev, - It is the responnibility of the p.lant m ner to provide A
for the establishesnt and execution of s systen of. sudits of the quality assurance pro;;eam for chc plant consistent with the provisions of this 4
4, standard.,The plant owner =sy delegate the uork of establishing and 5
executing audits but shall retsin responsibility to assure overall 6
ef fcctivenau. Such deley.tions shall be documented.
In no vsy shall 7
the perfo:=snee cf sudits by an organization operate to diminish the. respon-8 sibility of eny other organixstion or contract.or for audit of.his designated 9
portion of the quality assuranen pronram.
10 1.4 Orcenin-rfon - The erdanizatronsl structure, f,unctional responsibilitics, 11 levcis of. authority, and lines of internal and chtcrual cor' nication for u
12 s.nage= cat direction of sulits of the quality assurance program, shall be 13 docu=eb.ted.
Uhcre cultipic organizationel crrangements exist, the inter -
14 face.respon,sibilities of each organtxstion shall be elesrly defined and.
15 documented.
i I.
\\
. De,finit, ions - Terms and definitions are contsined in A1;SI K45.2 and 16 1.5
(,,
The follo.*ing definiticas are provided t.o assure a
~
.to unifor= understanding of sc1ceted terns as they are used in this 19 standard.
b!O 1.5.1 Audit - A for=al documented activity performed in accordance with.
21
' written procedures or checklists to verify, hy evaluation of 22 objective evidence, that a quality assurance program has been 23 developed, docu=ented and imple=ented in accordance with applicable 24 requirements of NiSI M45.2.
An audit does not include surveillsace 25
'cr. inspection for the purpose of process control or product acceptonce.
i 26 1.5.2 Ib~ tern.11 Audits - Audits of those' portions of an orgsnization's 27 quality assurance program retained under its direct control and 28 within its organizational structure.
U.
i Draft 3, Rev. t.s t
May 2, 1973
?_
. a.
\\
~
(
1.5.3 F.n:crnal.*otairs - A.udits of these portions of an organizations'
/
quality assurance progran not retained under its direct control f
b,3 n'nd not within its organizational strudture.
.Eri:. Either type of audit c:ay be perfortred by an organizations' 4
own personnel or by contracted personnel.
5 i
2.
PERS05:EL 6
7 2.1 Genern! - y.ansgn=ent shall be responsibic for select. ion and assignment of qualified auditors who are independent of any direct responsibility for.
8 9
the actJvitics which they will audit.
10 2.2 Persennel Gualific.uien - Managecent shall establish the audit personnel qualificacions app [opriata to the auditing of the quality assurance 11 Personnel shall be selected for quality assurance auditing 12 prograr.s.
)
(,
assiganents based on experience or training which establish that their l
qualifica tions are ec==ensurate ui3I.. ----~ -the compicxity or special naturc of the activities to be audited.
In sc.tceting personnel for auditing j
16 assignments, consideration shall be given to special abilitics, speciclized 17 technical trainin;;, prior per.tinent c3:periencea personal characteristics, 18 education, and physical capability. ANSI N45.2.6 is intended to be used
~
- ~ ~ ~..
19 asapproprictew[ththisstandarl_._
I 20 2.3 Trainine - Auditing personnel shall have, or be given, appropriate 21 training or orientation to assure their cocpetence for performing required 22 audits.
Co=petence of personnel for perfor=ance of the various auditing 23 functions shall be developad by one.or ::: ore of the following methods:
24 2.3.1 Orientation to provide personnel with working.imowledge and 25 understanding of both /SSI N4.5.2 and this standard.
~
8 i J Draft 3 Rev.
Eny 2,1973
_. _, _ _.. _ _ _ _ _ ~.,
~
i
(
2.3.2 Training progrecs de :igned to provide general and specialized training in nudi:; perfermance.
General training shall include i
3
. fundamentals, cbj ectives, charac teristics, organization, perf or-4 mance, and results of quality auditing.
Specialised training 5
shall inclulc nachods of c::smining, questioning, evaluating, and 6
docunenting sy=cific audit items, methods of identifying and 7
following up on corrective action items and methods of clusing 8
out audit findir.gu.
9 2.3.3 On-the-job training, guidsnce, and counseling under the direct 10 supervision of an enperienced, qualified auditor.
Such training shall include planning, performing, reporting, and foiloeup 11 12 action involv'ed in conductin's audits.
13 2.3.4 Orientation of technical specialists by the audit team 1cader.
14 Such orientation shall include familiarization with cudit prin-
[f' ciples and procedures.
(
16 2.4 Maintenance of Proficiency - Auditors shall maintain their proficiency 17 through one or more of the following methods:
18.
2.4.1 Regular, active participation in the audit process.
+
/
i 19 2.4.2 Revieu and study of codas, stendards, procedures, instructions, 20 etc., relat6d to quality assurance programs and program auditing.
}
21 2.4.3 Participation.in training or
- orientation programs as describcT 22 in.Section 2.3.
~
i t
(
4 Draft 3, Rev. 0
(
!!ay 2,1973 s
4 r.
4 I
3.
AUDIT SYSTO!
L 2
3.1 Cener.'.h - This section es tablishes requirements for a comprehensive 3
audit syrted which shall be planned, documented, and implemented to verify The audit 4
cc=pliance uith t.he cle=ents of a quality assurance pregram.
syster. shall t:e described in approved, written policies, plans, procedurei, 5
6 instructi::,ns, or such other documents as appropriate.- The objectives of 7
perfornir.c audits of the quality assurance program are:
8' 3'.l.1 To determina that a quality assurance program has been developed 9
and documented in accordance with the applicabis requirements i
10 of ANSI :245.2; i
i 11 3'.1. 2 To verify by evaluation uf objective evidence that the documented program has been i=plemented; 12
^
('
3.1.3 To asscas the affectiv ncsr. of the quslity assurance progr:n; 14 3.1.4 To identify progrc= nonconformanecc; and 15 3.1.5 To verify correction of identified nonconformsn'ces.
16 3.2 Tssectiel Elenenen of the Audit Svstem - An effective audit system shall 17 be estchlished and maintained and shall include the fc11ouing essential 18 elements:
19 3.2.1 A nanngement policy statement whf ch commits the organization to an 4
20 audit system eceting the requircecncs of'this stsudard.
l l
21 3.2.2 Manpoder, funding, and facilitics to impleecut ' he system of t
22 audits.
(-
.Dra ft 3, Rev. 0 s
p Hay 2, 1973 e
~
,o.
(
3.2.3 Identification of those responsible for the audit system, including -
\\
a delineation in the quality assurance program, of their authoritics 3
and respensibilitics.
4 3.2.4 Provisiens for reason::ble and timely access of audit personnel to f acilitier., docu. cats, and personnel necessary in the planning and 5
6 perfor=ance of the audits.
7 3.2.5 Provisions for reporting on the effectiveness of the quality assurance 8
program to the responsible management.
9 3.2.6 Access by audft personnel te manaccment having sufficient authority
- 0 to assure necessary corrective action.
L1 3.2.7 Provision for verification of corrective action on a. timely basis.
(
?
s.3 Audit ?lnnnine, - Planning of the audit sycte= shall be conducted te L -
assure coverage of the applicable quality assurance program, and overall L4 coordination and scheduling of audit activitics. This planning shall L5.
doce=ent creas of activitics, coverage, and scheduling of audits.- Audit L6 planning shall be periodically revictred and revised as necessary to assure 17 that coverage and schedule reflect current activitics.
18 3.4 S chedulin::
19 3.4.1 Auditing shall be initiated as carly in the life of the activity 20 as practicable, consistent tiith the schedule for accomplishing the activity to as_sure timely implementation of quality assurance requirc_-
21
.In_any__ case, auditing shall'be initiated early enough___g_a
~
22 ments.
23 as_sure effective quality assurance during the design, procurc=ent 24 and_contraeting activitics.
(l
(
(
s Drnft 3, Rev. O
\\
!!ay 2,1973 6
l o
(
./,
3.4.2 Aud,Lts shall be re;ularly scheduled on the basis of the status and safety ir.portance of the activitics to assure confornance 3
with t,he. developed chd implemented progran.
Applicabic elements, 4
of the quality assurance procrcm shall be audited at Icast
~~
5 annually or ac least.once within the life of the activity,-
6 whichever is shorter.
4 7
3.4.3 Sepplcacutal audits are condue cd for o$e er morc 'of the 8
following conditicas:
9 3.4.3.1 When it is necessary, to determine the capability 10 of-a contractor's quality assurance program prior 11 to awarding of a contract or purchase order'.
12 3.4.3.2 When, after award of a contract, sufficient time has f'
cinpned for inplementing the quality assurance pregrcs
- 24.,.
and it is appropriate to cetermina that the organization is adequately performing the functicus as defined in the 16 quality assurance program description, codes, standards, 17 and other contract documents.
18 3.4.3.3 When cignificant changes are made in functional aren_s i
19 of the quality assurance program such 'as significant, 20 re, organization or procedure revisions. _
I 21, 3.4.3.4 When there is evidence that the perforeance of reliability '
22 of safety-related iten in in jeepardy Muc to deficiencies 23 or nonconforcance in the quality assurance program.-
1 24
- 3. 4. 3. 5 When a systeentic, independent assessment of progran effec-23 tiveness of item quality, or both, is necessary.
Q Vs s
, J 1
Draft 3. Rev. O May 2, 1573 t
~
f, 3.4.3.6 'When it in neccesary to verify impIcnentation of rey:sf red corrective actions.
j
- 4.. AUDIT IH?LCIENTATIG'i 3
4 4.1 Cene.rnl - Individus) audits shall be implemented as scheduled and planned 5
in Section 3_., Ti:e cechanics involved in impic=entation 6f an audit are i
6 prepar=tica, perfor= nec, reporting, and follouup.,
PrEnnrarinn. - Preparation inciudes the development of a written audit 7
4.2 8
. plan, the sc1cetion and crientation of the auditor (s), and no.tification 9
of the or;nni:stion,co be audit.ed.
l 10 4.2.1* Uritten Plan - An individual audit plan describing the audit to, bc 11 perforced shall be developed and documented.
This plan chall identify 12 the audit scope, the requirements, the activities to be audited, the l(.>,
applicable docu=ents, the schedule, and written procedures or 1(
checklists.
15 4.2.2 Team Scicction - One or more individuals co$ prise an audit team,.
16 however, it in preferabic that a team of at least two qualified 17
,. individuals ' perform an audit Oh'e~ of 'the men [bNs.il N selected 18 as Daaer Ior'EAch audit tcan.
Ilin responsibilitics. include 19 orientation of the team, coordinating the audit process, establishin,r.
assuring communications uithin the team and 20 the pace of the audit, 21
.with the organization being audited, participation in the audit
~~
performance, and co._~dinating the preparation an.d issuance of 22 or
~
23 reports.
{(/
Draft 3, Rev. 0
'(-
Itay 2,1973 8
,._c-
..--,.-m..,_ _.,,,, -- -
s
~
Ten, oric testion - The team leader shall assure that the audit
(
4.2.3 team is prepared prior to initiation of the audit.
Pertinent l
.?
l Folicies, procedurcs, standards, instructicns, codes, regulatory 1
3 l
4 requirc= cats and prior audit reports, shall be :r.ade availabic for inferrhtion and retics by the auditors.
Each auditor shall be 5
provided with the audit plan and the procedurcs or checklicts uhich-6 are nccascary to a$ cure orderly accomplishment of the audit. During
(
1 7
the f =iliarir.ation phase of the audit, particular attention shall 8
be directed t ard internal and external' org:ni.zational and con -
9 tractus 1interfacesandresponsibilitiesoftheorganizai:Lontobe LO L1 audiced.
I
!otificI. tion - Involved organizations shall be notified of 12 4;2.4 Audit 13 a scheduled audit a reasonabic time before the audit is to be ti ' "
This notification chould be in uriting and inciude. -
~
14 perforced.
~
schedule of general infor=ation on the scope of the audit, 15 meetings and nethod of audit.
Unannounced audits may be perforned 1
- ith pric: :greem:nt of the parti: in :1::d.
18 4.3 Performance 19 4.3.1 Prc-Audit Conference - A brief pre-audit conference shall be con-ducted at the audit site with cognizant organization manc3ccent.
l 20 The purpose of the conference shall be to confirm the audit secpe, 21 l 22 present the audit plan, introduce cuditors, meet counterparts, discuss audit sequence, =nd establish channels of conmunication.
23 24 4.3.2. Audit Process 25 4.3.2.1 Checklists or procedures shall be used to ensure depth and continuity of audits.
~
26 4.3.2.'2 Objective evidence shall be examined for compliance with 27 quality assorance program requirements.
28
((
s
).) "
DrafC 3, Rev. O 9
May 2, ' 1973
4
('
4.3.2.3 *S$lected cicnents of the quality assurance progr.ua shall
'be audited to the depth necessary to determine whethe.r or
~
'i not they.sre being performed effectively.
3 r-4 4.3.2.4 When any nonconformance is found by an sudit. furth er invest.igstion shall be conducted in an effort to identify 5
the basic cause of the nonconformance.
6 7
4.3.2.5 Elements found to be nonconforming sliould be acknouledged
~
by a Eember of the audited org:nization.
8 9
4.3.2.6 Nonc,onfor:snces shall be reported at the post audit con-4 10 ference. Those requiring ic=ediate corrective action 4 mediately.
shall be reported to management 11 19 4.3.2.7 Specific attention should be given to corrective action'
(
of nonconfor=caces identified'during previous audits..
h
\\
14 4.3.3 Pg.r Asidit conference - At the conclusion of the audit a post audit conference shall be held with management of the audited organization.
15 An cf fort shall he cada to clarify Nisundcistandings, and reach 16 17 agreement on findings which constitute quality assurance progras 18 nonconfor=saces.
An' effort shall also be made to estsblish a ten-tative course and schedule of cdrrective action for each nonconfor-19 20 mance.
23 4.4 Rpoe ting - An sudit. report shall be written and signad by the audit team 24 leader t/nich provides 25 4.4.1 Def.cription of the audit scope 26 4.4.2 Identification of the auditors 27 k.4.3 Persons contacted U
8(
f Draft 3, Rev. 0 (
s
(
May 2, 1973 10
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2 5.2 Aut' ? t it.:cerd t 1:ecerda r.hn11 bc. ncr:.ted and retained for all audits.
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Kecords ehall include over.211 pre;;ro:: plans and statu::, inelividual nudit
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pla:ts, pertinent.erre..r.in.hn::e related to audits, audit reporte and s
4 ur3.tten replica,,.the s'.r.tus of re:1ui ted correcti/e act.f ons, nn:t docu :en ts 5
a:Ineciated stit:i ri.: cendurt of an.!its or deco:-ents schich nupp..rt audit 6
findia;..; and coercs' tive nction::.
7
.% 3 perso -
s'
':. cor.:4 - Recorda shall bc :::lintained for r.ll perconr.el actively 8
pe r forni:. : ati.:itn 29 uell an thore t:ho havn pre / lour,1y perforced audits 9
within the ::cr..: pre.i c et or activity.
p.ecordr shall include the records of 10 the qua!1ri c.it I.sn.; and tr..inin;; of auditor:..
i
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Draft 3, Rev. 0 May 2, 1973 J%
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JOB NO. 35-1195 6210ana Avenue, N. E.
rag lyg Wanen, Ohio 44481
^
Telephone (216)399-7666 Orc v i1977 November 17, 1977.
LCLl \\t E REIERENCE:
Comanche Peak Order Number CP-0046A, ITT Grinnell Lincoln Park Branch S.O. Number 31025-26, Warren Plant Register Number E-CM-026 Gentle =en:
We, ITT Grinnell Corporation-Pipe Hanger Division, certify that the materials supplied on the referenced order comply with all the applicable requirements of ANSI 331.1-1973.
We also certify that the fabrication complies with the applicable requirements of ANSI 331.1-1973.
H.O.
trom i
Quality Control Manager ECS/sar i
I j
cc:
R. Gospodarski, Providence B & R DCC DIST. _
DODD l
HOOG INFORMATION COM k
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O KIRKLAN O,1, 9o? \\
ARMS s
boc %(udLuG Executive CIfices/ Providence. Rhode Island l
wra,os.s:2 O s acss, III(.
t=amenos oasisms::s. constzuctocs "
New voan
% QUALITY CONTROL RELEASE SURVEILLANCE STATUS REPORT G & H, Inc. P.O.C FO V4B _ SUPPL. NO.(S)
,7 Date: //-/ 7 ' 7 7 VENDOR WORK / SHOP ORDER NO. f Cm C*2, 6 G & H, INC. PROJ.NO.
/ 2 ~ 2 212 T#/
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I SATISFACTORY OUALITY CONTROL RELEASE ONLY-OBTAIN G S H,Itc.
PURCH.0FPT. AUTHORIZATION TO SHIP NOT SATISFACTORY CONDITIONAL CUALITY CONTROL RELEASE-SEE COMMENTS REWORK AS INDICATED BELOW INTERME0 LATE SURVE!LLANCE ONLY HOLO FOR FURTHER INFORMATION, SEE COMMENTS COMMENTS BY G S H,INC. O.C. REPRESENTATIVE:
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L 7-This Status Report Does Not Rolleve The Vendor Of His Contractual Responsibilities, COPIES TO: (1) PURCHASING DEPT.
(I) VENOCR (I) 0.C. OEPT.
Ma me O-L. Oo (1) PROJ. MGH.
Glks & Hill,Inc., Representative 1
F.84 Rev 1.- 6/76
g s M Wg F %fYlG /
Ti.lP._ rid!
ITTGrinnellCorporatica 621DanaAvenue, N. E.
Wanen, Ohio 44461 Telephone (216) 399-7566 November 17, 1977 BIFERENCE:
Comanche Peak Order Number CP-0046A, ITT Grinnell Lincoln Park Branch S.O. 31025-21, Warren Plant Register Number E-CM-021 Gentle =en:
We, ITT Grinnell Corporation--Pipe Hanger Division, certify that the materials supplied on the referenced order comply with all the applicable requirements of ANSI B31.1-1973.
We also certify that the fabrication complies with the applicable require =ents of ANSI B31.1-1973.
4Property "ANSI code" (as page type) with input value "ANSI B31.1-1973.</br></br>4" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. m
i H.O.
rom Quality Control Manager HOS/sar cc:
R. Gospodarski, Providence INFORingl0NM
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STATUS OF ITEM (s) AFTER SURVEILLANCE:
e S ATIS FACTORY OUALITY CONTROL RELEASE ONLY-OSTAIN G S H, loc.
PURCH.0FPT. AUTHORIZATION TO SHIP NOT SATISFACTORY CONDITIONAL QUALITY CONTROL RELEASE-SEE COMMENTS REWORK AS IN0lCATED BELOW INTERMEDIATE SURVEILLANCE CNLY if HOLD FOR FURTHER INFORMATION, SEE COMMENTS COMMENTS SY G S H,INC. O.C. REPRESENTATIVE:
- s lb OL ff O m b ll f A r 't' a sa m.
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This Status Report Oces Not Rolleve TheVendor Of His Contractual Responsibillfles, COPlES TO: (I) PURCHASING DEPT.
(I) VENDOR (I) 0.C. OEPT.
/%uur 2,8a/
(1) PROJ. MGR.
Gibbs & Hill,Inc., Representative F.44 Revl.* 8/76
(..
7FL[j'jliu r
'f ITTGrinneliCorporatica 6210anahenue, N. E.
Warren, Ohio 44461 Telephone (216)399-7566 November 17,1977
REFERENCE:
Comanche Peak Order Number CP-0046A, ITT Grinnell Lincoln Park Branch S.O. Number 31025-22, Warren Plant Register Number E-CM-022 Gentle en:
We, ITT Grinnell Corporation--Pipe Hanger Division, certify that the materials supplied on the referenced order comply with all the applicable require =ents of ANSI 331.1-1973.
We also certify that the fabrication complies with the applicable requirements of ANSI 331.1-1973.
O
_ ///
H Stres Quality Control Manager EOS/sar R. Gospodarski, Providence cc:
'INFORugl03Cd V:
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Execudve Ctficestfroddence, Rhode Island
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OUALITY CONTROL RELEASE ONLY-OSTAIN G S H,Iric.
4 SATISFACTORY PURCH.0&PT AUTHORIZATION TO SHIP j
CONDITIONAL QUALITY CONTROL RELEASE-NOT SATISFACTORY SEE COMMENTS REWORK AS INDICATED BELOW INTERME0f ATE SURVEILLANCE ONLY HOLD FOR FURTHER INFORMATION, SEE COMMENTS e
COMMENTS SY G & H,INC. O.C. REPRESENTATIVE:
5 a JJ e m ), / r 93
.Z
(* c. e y c -
l_ o u e m r ec a i
- r. - r aew wennuutt0MCOP[
,,,,... ~ - -
=,
l-This Stofus Report Oces Not Relleve The Vendor Of His Contractual Responsibilities.
COPIES TO:(1) PURCHASING DEPT.
(l) VENCOR (l) 0.C. O EPT.
(l) PROJ. MGR,
'/),, _ y _ {] ),
( Gibbs & Hill,Inc., Representative l'80 Rev l.= 8/76
3 (.' < K.M CoLHr0Q y
7
' ! 'J.I. ! c : i u;
- _ j,1_. _ --
lIIGrinnellCGfpondon l
621 Dana Avenue, N. E.
Warren, Ohio 44461 Telephone (216)399-7566 November 17, 1977
REFERENCE:
Comanche Peak Order Number CP-0046A, ITT Grinnell Lincoln Park Branch S.O. Number 31025-13, Warren Plant Register Number E-CM-013 Gentl'emen:
We, T.TT Grinnell Corporation--Pipe Hanger Division,. certify that the materials supplied on the referenced order comply with all the applicable requirements of ANSI B31.1-1973.
We also certify that the fabrication complies with the applicable requirements of ANSI B31.1-1973.
lA
^
.. a H.O.
.cm Quality Control Manager EOS/sar ec:
R. Gospodarski, Providence INFORM s
i 1
$% c-Q 4,
......e k, d'c % V "o, +,/
f;;,+
Execudve Offices l Providence RhodeIsland
wroos t-1 Mill, Inc emOmteOS otS8CNCCS ComStavC7C#3 New Yoma 7 QUALITY CONTROL RELEASE O SURVEILLANCE STATUS REPORT G S H, Inc. P.O. CN V4 A _ SUPPL. NO.(S) -
2 Date: //-/ 7 ' 2 7 i
VENDOR WORK / SHOP ORDER NO. f_ om - O/J G & H, IN C. PROJ. NO.
/ 2 '2 J 2 8"J~C /
VENDOR I 7 '7" C va n n all LOCATION:_w n e e en, c h a'et ITEM (s) 14 C ge o r ^ H Om A l a e*/
C o c- *.
OWG. NO.( s)
T V s-b,,, Q r o n l* $,e vlu Y 6t~
STATUS OF ITEM (s) AFTER SURVEILLANCE:
SATIS FACTOR Y OUALITY CONTROL RELEASE ONLY OBTAIN G S H, tric.
/
PURCH.0FPT. AUTHORIZATION TO SHIP I
NOT SATISFACTORY CONolTIONAL QUALITY CONTROL RELEASE-SEE COMMENTS REWORX AS IN0lCATED BELOW INTERME01 ATE SURVEILLANCE ONLY HOLO FOR FURTHER INFORMATION, SEE COMMENTS COMMENTS BY G & H,INC. O.C. REPRESENTATIVE:
/ 'l Q 1J" t%, } / > c1' 2,.
c e,. r s, _ r
~
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,a o a
INFORMATION COPY
.,,..,.. s.. s.. - "
- This Status Report Does Not Relieve The Vendor Of His contractual Responsibili COPlES TO: (I) PURCHASING DEPT.
(1) VENDOR (l) Q.C. OEPT.
(l) PROJ. MGR.
/Zus =- /.Oab
~ #
Gibba & Hill,Inc., Representative 7.44 Rev i.* 0/76
wnw w a %aeanoa.esst; b'
t=simeros ossis=tas constcuctons '
~.. vc..
y QUALITY CONTROL RELEASE SURVEILLANCE STATUS REPORT G & H, Inc. P.O.docW A _ SUPPL. NO.(S) 8 Octe: / /- / 7 - 7 >
VENDOR WORK / SHOP CRDER NO. ECM C f /
G & H, INC. PROJ.NO.
/ 2 - 1121-f O /
VENDOR I TT G cn n n n //
_ e h lc LOCATION:
m,aeeen ITEM (s) NaavPc o1?em1,/, h Cor.
OWG. NO.(s)
C t e r uta To ha vu c, T t C rntQHo J True ro e 9 STATUS OF ITEM (s) AFTER SURVE!LLANCE:
SATIS FACTORY QUALITY CONTROL RELEASE CNLY-08TAIN G 8 H, tcc.
PURCH.0FPT. AUTHORIZAT!ON TO SHIP NOT SATISFACTORY CONDITIONAL QUALITY CONTROL RELEASE.
SEE COMMENYS REWORK AS IN0lCATED BELOW INTERME0 LATE SURVE!LLANCE ONLY HOLD FOR FURTHER INFORMATION, SEE COMMENTS COMMENTS SY G & H,INC. Q.C. REPRESENTATIVE-lb et f/ e m A /lM 2
r ar ro m
~
iNFORWAlloll COPY i
........ e... < ' "
- Thie Status Report Does Not Rolleve The Vendor of His Contractual Responsibilities.
COPIES TO:(l) PURCHASING DEPT.
(1) VEN00R (l) Q.C. O EPT.
//me,r4,8g (I) P8tOJ. MGR.
Gib6e & Hill,Inc., Representative
~
7.8 d J.
Revl. 8/76
.i t
+
PREIGHT T R A P'F I C' DEPARTMENT Checking List (Outbound)
Register No.
E-CM-013-00 1
T Contract No.
~ ((
19 77 Contract Name Car No.
Location No.
Weight No.
Sm Bulk Ccntainer
- O
'c Crates, C. S. Hgrs on Skid, Var. Spring Lg Dulk Container l
Ctns, C S Hgrs N
on Ski t.,
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N
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Bags, Hangers Pcs, Angic Iron Loose Hangers I
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Bdis, I-Bean
'1\\ibes, All-Thread
)
PCs, I-Beam Loose Pipe Stands IO Bdis, Pipe Boxes, Shock Suppr.
Pcs, PI C P
Bdis, Plate Bdis, U-Bolts PCs, Plate Pes, U-Bolts Bdl, Tubing l
Bdis, Rods-Rd Iron Pcs, Tubing
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Rod, Random db o/$
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,E CP 0046#
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_ _._ f.
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, aem T PAChilW UUrT-TO SOD Texas Uti.\\
egf Gen. Co.
[DATE I ITE;.t l grf TO 2001 Bryan;T r
.. -.... 5._i_ C
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9 Dallas,-Texasf75201 Y,h CS n
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.s c/o Texas Utilities' Services, Inc.
t f
Somervi.lle unty, Texas g
9 1
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Unit Price "" \\
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.......i.
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' FABRICATION. TYPE,
j YES NO QA REQUIREENTS STANDARD IF YES 3
~
d DOCUMENTATION SEE NorE (l
1 SPECIAL --SEE NOTE (
)
[_.J.
[td IF YES CUSTOMER INSP, SEE NOTE (
l l ~ NF NUCLEAR - SEE NorE (,
)
[_],R CODE INSPECTION
,1 l
NF "N" STAMP - SEE NOTE (
)
U R
OTER - SEE NOTE
(
f
MATERIAL CLASS BILLINC..,_____.
L l
I NUCLEAR CLASS I d
UNIT PIIGE 7
INrv5NINIIUN UUI"Y l
I NUCLEAR CLASS II OR III LUMP SUM IN ACCORDANCE WITH
!._._l NUCLEAR CLASS M.C.
r LRPTER DATED LP } B31.1
- p SHIPP iST - SEE NorE
( 3.)
{! crrER - SEE NOTE
(
)
MAIUKN - y,,
EE;NOTEF
(
)
TES NO, FAERICATION REOUTRED SkPI A
- SEE NOTE (l
)
.L 1
7
' PAINT FC-49-IF NO, SEE NorE('2-)
ADDI4 MA.
STRUCT'l; IS f y,'
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)
gg gpj NDE REQ 8D - SEE NorE
'(' )
A M **
~
/Ars DOUBLE NUTTING REQ'D.
SEE NEXT SHEET FOR N0rES & SPECIAL i
IF NO STANDARD PACEING.SEE NOTE ( -)-
INSTRUCTIONS
/A ' G c,'
i 2 (201 \\. o f Robs RIGINA
g Pipa.Han?pr,-Ehg.
- t. c F"
# 2...:.
,_ _ 'T j't,...,,.
Ssction I ~
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/ 5H'NING ORDER 340.
o
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PIPE If ANGER blVJ510N
_E-CM 013 CP-0046B Lincoln Park-31025-13 4/29/77 I
l REMIT SOLD Texas Utilities Gen. Co.
C
- 01 3 TO 2001 Bryan Tower Dallas, Texas 75201 L
1 r-1 SHIP Comanche Peak Stm. Elec. Sta.
TO c/o Texas Utilities Services, In c.
Somerville County, Texas 6
^
L l
PAGE or h
J Unit Price 2
5 Best Way Ppd & Charged.
Warren sin m;..ein e I
I
,q.#".^-}.' '.";. g' u, _ l J.',';,,. ' em
- m:ood i
l 1
l' 1)
The following documentation and records shall be transmitted prior to shipmenti 2
original and two (2) copies of bill of ladl~ng, ituo TF))~i:fopfes ff packing listi,'
_ ~
original and one (
conv of freight bill to:
boxas Utilities Services,Inc.
3 2001 Bryan Tower, Da lie' Texas, 7:i201 Attihr Mr. If.'W.dexas Utillities Servicesca bill of lading and one (1) copy of packing listi to:
Inc. P.O. Box 1002, Glen Rose, Texas, yT0437KEth: Mr. c.n. Gatcliefl. iTwo (2:
copies of bill of lading and two (2) copies of : packing list to': Brown & ' Root, l 1
3
-~ --
Inc., P.O. Bo'x TO01, 51en Rose, Texas, (760437AEEn-~". H.C. Ed-~'
j l
2)
All material on this order to be painted with one (1) at of arbo zinc #12 except thYehds and threi~ded fasteners wEch shall be coated w'I'th a rust.;"
6 preventative.
. M On'date oTs711pment f6Mard the ~f611owing information by TW~tlo:
l Utilities Services, Inc. TWX 910-890-8660, Att2i: C.H. batchell!:
~
Texasi i
a - 1Eid:idr"of liis~csE b6xhs bH'dles b - Gross weight of each package, etc.
~~
d - scheduled date of departure from or{;i. gin l
c 'C'P5fn~t~of"origih of 'shi'pment
9
~
p e - sche ~duTdd'aa'ts 6f"iob' sit'e-Erfival to l
f - Proposed carrier and fputing l
9 - EsTotp rsI&tEd7 ' ion saf6tpElatet!Ter totti l
n r
i l
7
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O FRRIGHT T R A P'P I C DEPARTMENT i
Checking List (Outbound) g l ?
I Register No.
I Contract No.
N.51M. ELEC STA.
//. //
1, 77
. -.... IES SERVICES SW Et-Con' tract Name iILLE CTY. TEXAS Car No.
Location No.
Weight No.
Sa Bulk Container Crates, C. S. Hgra on Skid, Var. Sering Lg Dulk Conta:ner Ctns, C S Hgra on Skid, Var. Springs _
X !'
3
[
PCs, I-Beam NO Loose Pipe Stands Bdis, Pipe Boxes, Shock Suppr.
Pcs, Pipe Bdis, Plate Bdis, U-Bolts PCs, Plate Pes, U-Bolts N
Bdi, Tubing
)
Bdis, Rods-Rd Iron PCs, Tubing Rod, Randon Pcs, Rod-Rd Iron Skids, Clamps f,,,,,
Loose Clamps i
ye : ed ="
a
'IOTAL IIEIGHT O
CO J
~
%,., @_ Q.E. A,RBER. v,c u '77
" = i ' ' " ' '- '
- Q ' ~%. ' " '. brsis:4 4.';.b. ;7 ?'"~
. Scctir>n E '
( '
k
. I'lPli fI ANGillt I. t \\ id!ON (f./,,
E-CM O22,
J/;
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CP-0046$
Lincoln Park 31025-22 6/3/77
....o..
~
l f.
(1110) lREMir l
j.
a; TO
.h
,/
m' i i 70 Texas Utilition Gen. Co.
iomrei r,> -ry
- c, :
c.
t.
t.
2001 Bryan Tower
_S201.
Dallas, Texas
/
i L
'?ACXAG COnh' -022 H $3 i
3/M I~
T $
lRDM (x)!
l Comanche P,eak Stm. Elec. Sta.
i
' sagp H
c/o Texas Utilities Serv 1.ces, I gEctA s
TO e
j l' Somerville County, Texas
/
L
_]
unit erice
"" 1 1.,..
4
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[/,f 7[
m e,.
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... _ =
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l FABRICATIO;r TTPE,
yrs.
tro oA ggq'UIREtTiiTS i
g d STANDARD IF YES I
l DOCUMENTATIO:TSEEjr&E
(
. l l
SPECIAL - SEE NOTE (
)
I
- l. d IF YES CUSTOMSR INSP Sgg g a g (
l I ~ NF ITUCI. EAR - SEE NOTE ( )
[_] @
CODE INSPECTION c.[ l l
NF "N" STAMP - SEE NOTE (
)
R R
CrHER - SEE NOTE
(
c
[
MATERIAL CLASS t
,BILLI1ro
.Y L._)..NUC. LEAR C.L. AS S I....... _.. _
[E.]
UNIT PRICE NUCLEAR CLASS II OR III
$ UMP SUM IN ACCORDANCE WITH U
MUCLEAR.CIASS M.C.
e LETTER D'ATED 533 1. 1 L
SH SEE NorE (p
!.OTHER - SEE NOTE
(
)k,
. MA' R.s ' "
stb TNorE Y T
(
.YES NO FABRICATION REOUIaED
.SHIPPIN A ~'R'DI SEE NOIE (p'
f I )
Y PAINT FC-49-IF NO SEE
[Z)
ADDITIONA E TPUCTIONS g p -3 d,
i s
i j Y
SPEC. HEAT TREAT-SEE NOTE ( )SEE NOTES ~~(
/
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'^
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/ 1,.o &4-i rmE RE2'D - SEE rr0TE.
. (- )
7.
lilFORMAT10ll. COPY b
4 <
DOUBLE UUTTING REQ'D.
'D vS$E 'IfWSitEMuu aun,6"a.' SFECI'AL
1 7 n o J~
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~
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STANDARD PACKING.SEE NOTE ( ) $'
UISTHUCTI
/
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UfW
/-
,,-c.
ng I
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Pipe Hanger-Eng.
f "" i" 4"2..f. ?, " ff /*t,,,.,,,
I '.'i ti t t. w Srction I-s '.k 5'
'i'
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- l 'd"* *
- HO-l t.P' ;. ' u ai L.k._' s.* :~.r: i 1
PIPE HANGER DIV ION E 'Cth 022 j
n fqp0046B Lincoln Park-MO2.5-22 6/3/77
-i (AAlv) i l REMIT
.e.
TO
-SOLD Texas Utilities Gen. Co.
TO 2001 Bryan Tower C M- 02 2
-. Dallas, Texas 75201 L
J i
F-1
~
Comanche Peak Stm. Elec. Sta.
~~
SHIP I
TO c/o Texas Utilities Services, In c.
Somerville County, Texas
.4J l
I PAGC Op.
il L.
J Unit Price 2
4 h..
E}
Best Way Ppd & Charged Warren J.-,-
eu.,.T.
l i
i
- .~'v.
seu on.e.c m.w erscount
,, - --.- ;;,;. i
_ i u ts.. m i
l l
l.
1)
The following documentation and records shall e tran.< unit _t,ed pr orl~ifia'l and tuo (2) Edipie~s Tf Eff of ladlng, [Eio' T2)] copie_s,p_i_or,,t.o _ ship::._e 2-e packing lis:
(
original and one.g.),llas Texas, 7526f Attn: copy o_f freight bill _to:. Texas U,tilitie
'e 3 2001 Bryan Tower, Da Mr. R.W_..,Caudle. One '(1) copy o.
j bill of lading and one (1) copy of packing listi to:
Tenas _Utitlitics Servi,ce*
L Inc. P.O. Box 1D02, Glen Rose 7 TeicE's, KO~4Y," A'EtH'i' 92.- 6.'li. Gitiihefl. !Two :
d l
cop es_of bill o l_
Inc., P.O. Box 1.f 1.a_d.i..n7 and two (2) copies.4 f._pa.c..ki__ng list to:
o Brown &' Root, 00, Gfen Rose, Texas,
- 7 60 3,.AT tn
- M.r. H.C. Dodd s
! '+Q_ All material on this order to be painted with one (1) ' coat of ;ccrbo zinc; #,1),
J except tliFcaifs"aliftHFeE3cTH:teners unl a.cn shT1TLe ii6dted wTth'~ a ru d,f preventative.
late of sh'iW. erit idE7ard tifie~f611ow).ng IIif6h~IaT. ion lby TWX E[o:
t 3)
On
'1'exa s.
d Utilities Services, Inc. TWX 910-890-86E.0, Attri: C.H. 'Catchell':
j
'M a 'r MGmbH 'ofpi' ecee'b6xd6 bSfdles
~~~
~
6 h
b - Gross weight of each package, etc.
l 4
c r P6' int ~of~ ori~ gin of 'shitt.nent"---
j l
d - scheduled date of deoarture from origin
, ' ~
~~
Fj E - sareT:suled date ot Sossite'arrivur -
io p
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TO TO 2001Bqan Tower Dallas, Texas 75201
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2001 Bryan Towar, Da las~ Texas, Mr. R.W. raudl_e
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'ie::as Uti'lities Services
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Inc. P.O. Box 1.0d2, G13n"idi5e7 Texas,
)M4Y,'~KEtn i EIt.'~(f.'II. G'aYdien. i67o"(
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Inc.,
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- g na f
U.S. NUCLEAR REGULATORY COMMISSION February 1978
@\\/j ! REGULATORYGU DE
! [)
OFFICE OF STANDARDS DEVELOPMENT y
k REGULATORY GUIDE 1,33
{'
OUALITY ASSURANCE PROGRAM REQUIREMENTS (OPERATION) i A, INTRODUCTION ANS-3.2, " Administrative Controls and Quahiy As-surance for the Operational Phase of Nuclear Power I
Appendix B, " Quality Assurance Criteria for N.
Plants,"' by the Amencan National Standards insti-u-
clear Power Plants and Fuel Reprocessing Plants, t tute on Februarv 19, 1976.
1 10 CFR Part 50, " Licensing of Production and Utih-zation Facilities " establishes quality assurance re.
There had been some uncertainty with regard to the l
quirements for the operation of nuclear power plant NRC staff 1 position when a regulatory guide en-safety-related structures, systems, and components.
dorses, as an a'ceeptable method, the " guidelines" as This regulatory guide describes a method acceptable well as the " requirements" included in a standard.
]
to the NRC staff for complying with the Commi,-
The NRC staff has evaluated the guidelines contained sion's regulations with regard to overall quality as-in N18.7-1976/ANS 3.2 with respect to importance surance program requirements for the operation phase to safety. Revision 1 of this regulatory guide c!arified of nuclear power plants. The Admory Committee on the NRC staff's position on the " requirements" and e
Reactor Sateguards has been consulted concerning
" guidelines" included in ANSQ18.71976/ANS-this guide and has concurred in the regulatory 3.2. Where conformance to the recommendations of I
position.
this regulatory guide is indicated in an application 4
l without further qualification, this indicates the appli-cant will comply with the ' requirements" of ANSI B, DISCUSSION N18.7-1976/ANS-3.2, as supplemented or modified Subcommittee ANS-3, Reactor Operations, of the by the regulatory position of this guide.
American Nuclear Society Standards Committee de-veloped ANSI N18.7-1972, which contained enteria for Section I, " Scope," of ANSI N18.7-1976/ANS-administrative controls for nuclear power plants dur-3.2 states that this standard contains criteria for ad-ing operation. This standard, along with ANSI ministrative controls and quality assurance for nu-N45.2-1971 " Quality Assurance Program Require-clear power plants during the operational phase of ments for Nuclear Power Plants," was endorsed by plant life and that this' phase is generally considered Regulatory Guide 1.33. The dual endorsement was to commence with initial fuel loading. except for cer-necessary in order for the guidance contained in the tain preoperational activities. In this regard, a sepa-regulatory guide to be consistent with the require-rate regulatory guide addressing the quality assurance ments of Appenda B to 10 CFR Part 50; however, program for the preoperational phase will be issued.
this dual endorsement caused some confusion among Other regulatory guides may be issued or this regula-users. To clarify this situation, ANSI N18.7-1972 tory guide may be revised, if necessary, to amplify was revised so that a single standard would define the the general requirements contained in this standard.
general quality assurance program " requirements" for the operation phase. This revised standard was Appendix A to this guide has been further revised as a result of additional comments received on the approved by the American National Standards Com.
mittee N18, Nuclear Design Criteria. It was sub.
guide and additional staff review.
sequently approved and designated N18.7-1976/
' Copies may be obtained from American Nuclear Society, 555
- Lines inJacaic substantive changes from previous inue.
North Kensington Asenue. La Grange Park, Ilhnois 60525.
USN RC REGULATORY GUIDES co=~ at e pow t>r ieat tu ~ s= ce,.d ~ comnott.om us Nucie, New Rewletut y Guales are ethod to descrits and make avJdet9e to the public tr'ethodt n
attestanie to the %RC staff of sm6dementmq topedet pats of the Cummes on t regu t..nt io nee.neeee set ha auet used by the staf f en ewoucing quer e.C pect:6ernt The quases me esucit en the ta k vig te,* tvo.s d.vuons a
n s
sW tastf uleted 4Ct ateftts. Or 90 pruende guede'tCe 10 SDpleCentt Regulattw y Gualet de ftet bbie ntutet fut tegutelser*t. Snff CUmpioenCe steth therTt et foof reauweq$
- 1. POUD8't N edCt ar t 6
,e udurt t Reteach errt Tett Reactewg 7 f rangneptet ua Methtirft enet ggdutoont d'Herent feerrt th09e let Out en the guettet emell be attept
. =-. _.. -.. -.. _. _ =. - _ =. -. _. -.
==
=
==
, o.,et,s d,1.pt e,
io oe e...
twriet and guedet edl tie rewete1, et eporOpraete to accomettodete Cornfutentt and
, Rent on sat autornetat fl4te ihunna 4.te 6,y gerup,, op.eg sd 4 t.,ne aguates en tiprd==
to retiert etest satOternetson Ut esper' ente Th4 guW9e *dt 'ow'tell #6 4 fetult 00 Ger'sent thssu st he nadstus est que.togg tu H=e U s Nutt** tteei te'tW e Lom'n'euen e
htlStantive COrnrhentt Ferg.werf from the publet eftE9 ark 9stsen# Stett feweeue Wethenet Es*1 OL M A Hent -8**
Ue 8t tes U'W*t'un ( A D'4 4* '*t ( * ' t'G' em w ccan P0lA-85-Sh i
l C. REGULATORY POSITION and will be endorse" ty a regulatory guide The overall quality assurance program require-upon its approval a'
.1 ANSI standard.
ments for the operation phase that are included in ANSI NI8.7-1976/ANS-3.2 are acceptable to the
- 3. Section 4.3.4, " Subjects Requiring Independ i NRC staff and provide an adequate basis for comply-ent Review," Item (3) states, in part, that changes to ing with the quality assurance program requiremer:ts the technical specifications or license amendments re-of Appendix B to 10 CFR Part 50, subject to the fol-lated to nuclear safety are required to be reviewed by lowing:
the independent review body prior to implementaeon.
It should be noted that proposed changes to technical I. ANSI N18.7-1976/ANS 3.2 requires the prep-specifications or license amendments should be re-aration of many procedures to carry out an effective viewed by the independent review body prior to their g
quality assurance program. Appendix A, " Typical submitral to the Commission for approval.
/
Procedures for Pressurized Water Reactors and Boil.
ing Water Reactors, to this regulatory guide should
- 4. Sect on 4.5 " Audit Program," of ANSI
/
be used as guidance to ensure minimum procedural NI8.7-1976/ANS 3.2 states that audits of selected }
coserage for plant operating activitics, including re-g lated maintenance activities. Appendix A lists typical g
gg safety related activities that should be cosered by
- g; written procedures but does not provide a complet that an audit of all safety-related functions is com-listing of needed procedures. Many other actmties pleted within a period of 2 years. In amplification of carried out during the operation phase of a nuclear g
power plant require written procedures not included should be audited at the indicated frequencies:
in Appendix A. Appendix A may also contain proce-
- a. The results of actions taken to correct de-dures that are not applicable to an applicant because ficiencies that affect nuclear safety and occur in facil-of the configuration of the nuclear power plant. The ity equipment, structures, systems, or method of procedures hsted in Appendix A may be combined, operation-at least once per 6 months.
separated, or deleted to conform to the applicant's
- b. The conformance of facility operation to pro-procedures plan.
- 2. Throughout ANSI N18.7-1976i ANS-3.2, other v sions contained within the technical specifications documents required to be included as a part of this and applicable license conditions-at least once per standard are identified at the point of reference. The 12 months.
specific acceptability of these standards listed in
- c. The performance, training, and qualifications I I
ANSI NI8.7-1976/ANS-3.2 has been addressed in the latest revision of the following regulatory guides:
of the facility staff-at least once per 12 months.
- 5. The guidelines (indicated by the verb ANSI Standard Regulatory Guide
- should") of ANSI N18.7-1976/ANS-3.2 contained l
N45.2 1.28 in the following sections have sufficient safety impor-N45.2.1 1.37 tance to be treated the same as the requirements (in-N45.2.2 1.38 dicated by the verb "shall") of the standard:
N45.2.3 1.39 N45.2.4 1.30
- a. Section 4.4-The guidelines concerning re-view activities of the onsite operating organization, N45.2.5 1.94 except the guideline that refers to screening subjects N45.2.6 1.58 of potential concern.
N45.2.8 1.I16 N45.2.9 1.88
- b. Section 5.2.3-The gaideline concerning re-N45.2.10 1.74 view and updating of standing orders.
N45.2. l l 1.64
.13 23
- c. Section 5.2.4-The guideline concerning re-view, updating, and cancellation of special orders.
~
N 18.17 1.17
- d. Section 5.2.7.1-The guidelines that address N 101.4 1.54 adequate design and testing of replacement parts.
Nure: N45.2.12 is discussed in NRC
- e. Section 5.2.13.4-The guideline concerning documents WASil-1283, " Guidance on special handling tools and equipment.
Quality Assurance Requ!rements During Design and Procurement Phase of Nuclear
- f. Sect on 5.2.19(2)-The guideline for check-Power Plants, (Grey Book) and WASH-ing plant operating procedures during the testing pro-1309, " Guidance on Quality Assurance Re-E '**
- quirements During the Construction Phase
- g. Section 5.2.19.1-The guidelines for preop-of Nuclear Power Plants," (Green Book) erational tests, except the guideline that refers to a 1.33-2 i
i l
l run-in period for equipment. In addition to these tification in Section 5.3.9.l(2); automatic actions in l
guidelines, the prerequisite steps for each equipment Section 5.3.9. l(3); immediate operator action, I
test should be completed prior to the commencement excluding those guidelines contained in the examples, I
of the preoperational test.
in Section 5.3.9.l(4); and subsequent operator ac-s ti ns in Secti n 5.3.9.l(5).
- h. Section 5.3.2-The guidelines that elescribe i.
the content (excluding format) of procedures, except i
f for the guidelines that address (1) a separate state-D, IMPLEMENTATION 1
I l
ment of applicability in Section 5.3.2(2), (2) inclu-The purpose of this section is to provide informa-i sion of references in procedures, as applicable, in Section 5.3.2(3), and (3) inclusion of quantitative II ".t applic nts and licensees regarding the NRC staff s plans for using this regulatory guide.
i control guides in Section 5.3.2(6).
This guide cellects current NRC practice. There-i
- i. Section 5.3.9-The guideline concerning fore, except in those cases in which the applicant emergency procedures requiring prompt implementa-proposes an acceptable alternative method for com-tion of immediate operator actions when required to plying with the specified portions of the Commis-prevent or mitigate the consequences of a serious sion's regulations, the method described herein is I
condition.
being and will continue to be used in the evaluation
- j. Section 5.3.9.1-The guidelines that describe of submittals for operating license applications until the content (excluding format) for: the title in Section this guide is resised as a result of suggestions from 5.3.9.l(1); the inclusion of symptoms to aid in iden-the public or additional staff review.
t 9
l I
1 l
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I
APPENDIX A TYPICAL PROCEDURES FOR PRESSURIZED WATER REACTORS AND BOILING WATER REACTORS l
The following are typical safety related activities
- b. Control Rod Drive System (including part-that should be covered by written procedures. This length rods) appendis is not intended as an inclusive listing of all
- c. Shutdown Cooling System needed procedures since many other actisities carried
- d. Emergency Core Cooling System out during the operation phase of nuclear power
- e. Component Cooling Water System plants should be covered by procedures not included
- f. Containment in this list.
(1) Maintaining Con ainment Integrity (2) S ecial Containment Systems f
P 1.
Administrative Procedures
- a. Security and Visitor Control tmos heric
- b. Authorities and Responsibilities for Safe Opera-(c) Double-Wall Containment with Controlled tion and Shutdown Interspace
- c. Equipment Control (e.g., locking and tagging)
(d) Ice Condenser
- d. Procedure Adherence and Temporary Change Method (3) Containment Ventilation System
- e. Procedure Resiew and Approval (4) Containment Cooling System
- f. Schedule for Surveillance Tests and Calibration
- g. Atmosphere Cleanup Systems
- g. Shift and Relief Turnover
- h. Fuel Storage Pool Purification and Cooling Sys-
- h. Log Entries, Record Retention, and Review tem Procedures
- i. Access to Containment
!. Main Steam System
- j. Bypass of Safety Functions and Jumper Control J. Pressurizer Pressure and Spray Control Systems
- k. Maintenance of Minimum Shift Complement
- 1. Auxiliary Feedsvater System
- l. Plant Fire Protection Program
- m. Service Water Systera
- m. Communication System Procedures
- n. Chemical and Volume Control System (includ-
- 2. General Plant Operating Procedures ing Letdown / Purification Systen)
- o. Auxiliary or Reactor Bt.ilding HeatinF and
- a. Cold Shutdown to Hot Standby Ventilation
- b. Hot Standby to Minimum Load (nuclear start-
- p. Control Room Heating and Ventilation up)
- q. Radwaste Building Heating and Ventilation
- c. Recovery from Reactor Trip
- r. Instrument Air System
- d. Operation at Hot Standby
- s. Electrical System
- e. Turbine Startup and Synchronization of (1) Offsite (access circuits)
Generator (2) Onsite
- f. Changing Load and Load Follow (if applicable)
- g. Power Operation and Process Monitoring (a) Emergency Power Sources (e.g., diesel
- h. Power Operation with less than Full Reactor generator, batteries)
Coolant Flow (b) A.C. System
- i. Plant Shutdown to Hot Standby (c) D.C. System
- j. Hot Standby to Cold Shutdown t.
Nuclear Instrument System
- k. Preparation for Refueling and Refueling Equipment Operation (1) Source Range L
- 1. Refueling and Core Alterations (2) Intermediate Range (3) Power Range l
- 3. Procedures for Startup Operation, and Shutdown (4) Incore System of Safety-Related PWR Systems I
- u. Reactor Control and Protection System Instructions for energizing, filling, venting, dra.in-v.
Hydrogen Recombiner ing, startup, shutdown, and changing modes of oper-ation should be prepared, as appropriate, for the fol-lowing systems:
- 4. Procedure for Startup, Operation, and Shutdown Reactor Coolant System of Safety-Related BWR Systems a
1.33-4
i I
Instructions for energizing, filling, venting, drain-
- 5. Procedures for Abnormal. Offnormal, or Alarm i
Conditions ing, stanup, shutdown, and changing modes of oper-ation should be prepared, as appropriate, for the Since these procedures are numerous and corre-followmg systems:
spond to the number of alarm annunciators, the pro-cedures are not individually listed. Each safety-related annunciator should have its own written
- a. Nuclear Steam Supply System (Vessel and procedure, which should normally contain (1) the Recirculating System) meaning of the annunciator, (2) the source of the sig-
- b. Control Rod Drive System nal, (3) the immedate action that is to occur automat-
- c. Reactor Cleanup System ically, (4) the immediate operation action, and (5) the
- d. Liquid Poison System (Standby Liquid Con-long. range actions.
trol System)
- e. Shutdown Cooling and Reactor Vessel Head
- 6. Procedures for Combating Emergencies and Other f Hi h P essure Coolant injection Sigmficant Events
- g. Reactor Core Isolation Cooling System
- a. Loss of Coolant (including significant PWR
- i. Closed Cooling Water System steam generator leaks) (inside and outside primary containment) (large and small, including leak-rate
- j. Containment determination)
(1) Maintaining Integrity
. Loss of 1I er al wer (and/or degraded nd d e g
power sources)
- k. Fuel Storage Pool Purification and Cooling
- d. Loss of Core Coolant Flow
- e. Loss of Condenser Vacuum System
- 1. Main Steam System (reactor vessel to turbine)
- f. Loss of Containment integrity
- m. Turbine-Generator System
- g. Loss of Service Water
- n. Condensate System (hotwell to feedwater
- h. Loss of Shutdown Cooling pumps, including demineralizers and resin
- i. Loss of Component Cooling System and Cool-regeneration) ing to Individual Components
vess. Fcedwater System (feedwater pumps to reactor o
Failure el)
- p. Makeup System (filtration, purification, and
- k. Loss of Protective System Channel water transfer)
- 1. Mispositioned Control Rod or Rods tand rod drops)
- q. Service Water System
- m. Inability to Drive Control Rods
- r. Reactor Building Heating and Ventilation
- n. Conditions Requiring Use of Emergency Bora-tion or Standby Liquid Control System Systems
- s. Control Room Heating and Ventilation
- o. Fuel Cladding Failure or High Activity in Reactor Coolant or Offgas Systems
- t. Radwaste Building Heating and Ventilation
- p. Fire in Control Room or Forced Evacuation of Control Room Systems
- q. Turbine and Generator Trips
- v. Instrument Air System
- r. Other Expected Transients that may be
- w. Electncal System Applicable
- s. Malfunction of Automatic Reactivity Control (1) Offsite (access circuits)
System (2) Onsite
- t. Malfunction of Pressure Control System p
(a) Emergency Power Sources (e.g., diesel
- u. Reactor Trip j
generator, batteries)
- v. Plant Fires
~
- w. Acts of Nature (e.g., tornado, flood, dam V
(b) A.C. System (c) D.C. System failure, carthqu.kes)
- x. Irradiated Fuel Damage While Refueling
- x. Nuclear Instrument System y Abnormal Releases of Radioactivity
- z. Intrusion of Demineralizer Resin Into Primary (1) Source Range (2) Intermediate Range System (BWR Plants)
(3) Power Range
- 7. Procedures for Control of Radioactivity (For limit-(4) TIP System
- y. Reactor Protection System ing materials released to environment and limiting
- z. Rod Worth Minimizer personnel exposure) 1.33 5
- a. Liquid Radioactive Waste System (1) Pressurized Water Reactors (1) Collection, Demineralizing. Filtering, (a) Containment Leak Rate Tests Evaporating and Concentrating, and (b) Containment Isolation Tests Neutralizing (c) Containment Local Leak Detection (2) Sampling and Monitoring Tests (3) Discharging to Elfluents (d) Containment Heat and Radioactivity
- b. Solid Waste System Removal Systenu hsts (e) Containment Tendon Tests and (1) Spent Resins and Filter Sludge Handling Inspections (2) Baling Machine Operation (f) Service Water System Functional Tests (3) Drum Handling and Storage (g) Main Steam Isolation Valve Tests
- c. PWR Gaseous Effluent System (h) Fire Protection System Functional Tests (i) Boric Acid Tanks-Level Instrumenta-(1) Collection, Storage, and Discharge tion Calibrations (2) Sampling and Monitoring (j) Emergency Core Cooling System Tests (3) Air Ejector and Stack Monitoring (k) Control Rod Operability and Scram (4) Ventilation Air Monitoring Time Tests
- d. BWR Air Extraction, Offgas Treatment, and (1) Reactor Protection System Tests and Other Gaseous Effluent Systems Calibrations (m)Permissives--Tests and Calibrations (1) Mecham. cal Vacuum Pump Operation (n) Refueling System Circuit Tests f
(2) Air Ejector Operation (o) Emergency Boration System Functional (3) Packing Steam Exhauster Operation Tests (P) DNB Checks and Incore-Excore Flux A
j c or, Ventilation, and Stack Monitor Monitor Correlations
- e. Radiation Protection Procedures (q) Emergency Power Tests (1) Access Control to Radiation Areas includ-(r) Auxiliary Feedwater System Tests IS ing a Radiation Work Permit System (2) Radiation Surveys election (3) Airborne Radioa'ctivity Monitoring (t) Inspection of Reactor Coolant System I
s r to P o ec i n (u) ns ti n f Pipe Hanger Settings I
(6) Training in Radiation Protection (v) Control Rod Drive System Functional 8
(8 B as ay Progr (w) Heat Balance-Flux Monitor Calibrations (9) Implementation of ALARA Program
- f. Area Radiation Monitoring System Operation Valve Tests
- g. Proce.ss Radiation Monitoring System (y) Leak Detection Systems Tests
)
Operation (z) Axial and Radial Flux Pattern Determi-
- h. Meteorological Monitoring nations
- 8. Procedures for Control of Measuring and Test (aa) Area, Portable, and Airborne Radiation Equipment and for Surveillance Tests, Proce-Monitor Calibrations dures, and Calibrations (bb) Process Radiation Monitor
- a. Procedures of a type appropriate to the cir-Calibrations cumstances should be provided to ensure that tools, (cc) Environmental Monitor Calibrations gauges, instruments, controls, and other measuring (dd) Safety Valve Tests and testing devices are properly controlled, calib-(ee) Turbine Overspeed Trip Tests rated, and adjusted at specified periods to maintain (ff) Water Storage Tanks-Level In-accuracy. Specific examples of such equipment to be strumentation Calibration calibrated and tested are readout instruments, inter.
(2) Boiling Water Reactors lock permissive and prohibit circuits, alarm devices, sensors, signal conditioners, controls, protective cir-(a) Containment Leak-Rate and Penetration cuits, and laboratory equipment.
RmTm (b) Containment Isolation Tests
- b. Specific procedures for surveillance tests, in-(c) Containment Vacuum Relief Valve spections, and calibrations should be written (imple-Tests menting proceJures are required for each surveillance (d) Containment Spray System Tests test, inspection, or calibration listed in the technical (e) Standby Gas Treatment System Tests specifications):
(including filter tests) 1.33-6
{
l (O Service Water System Functional Tests
- c. Procedures for the repair or replacement of (g) Main Steam Isolation Valve Tests equipment should be prepared prior to beginning
]
9 (h) Fire Protection System Functional Tests work. Such procedures for major equipment that is (i) Nitrogen Inerting System Tests expected to be repaired or replaced during the life of (j) Emergency Core Cooling System Tests the plant should preferably be written early in plant (L) Control Rod Operability and Scram Time life. The following are examples of such procedures Tests for major equipment:
(1) Reactor Protection System Tests and (1) Repair of PWR Steam Generator Tubes (2) Replacement and Repair of Control Rod (m) Rod Blocks-Tests and Calibrations
) Replacement of Recirculation Pump Seals qui Poi o S st ss (4) Replacement of important Strainers and l
(p) Minimum Critical Heat Flux Checks and
)
Filters Incore Flux Monitor Calibrations (5) Repair or Replacement of Safety Valves (q) Emergency Power Tests (6) Repair of Incore Flux Monitoring System (r) Isolation Condenser or RCIC Tests (7) Replacement of Neutron Detectors (s) NSSS Pressurization and Leak Detection (t) Inspection of Reactor Coolant System
- d. Procedures that could be categorized either as Pressure Boundary maintenance or operating procedures should be (u) Inspection of Pipe Hanger Settings developed for the following activities. Instructions (v) Control Rod Drive System Functional for these activities may be included in systems Tests procedures.
(w) Heat Balance (1) Exercise of equipment that is normally idle (x) Autoblowdown System Tests (y) Leak Detection System Tests but that must operate when required (z) Axial and Radial Flux Pattern Determi.
(2) Draining and Refilhng Heat Exchangers nations (3) Draining and Refilling Recirculation Loop (aa) Area, Portable, and Airborne Radiation (4) Draining and Refilling the Reactor Vessel Monitor Calibrations (5) Draining and Refilling Steam Generators (6) Removal of Reactor Head (bb) Process Radiation Monitor Calibrations (7) Disconnection and Reconnection of Wiring Ol (cc) Environmental Monitor Calibrations (dd) Safety Valve Tests Penetrating Reactor Vessel Head
)
(ee) Turbine Overspeed Trip Test (8) Demineralizer Resin Regeneration or (f0 Water Storage Tanks-Level In.
Replacement strumentation Calibrations
- e. General procedures for the control of mainte-(gg) Reactor Building Inleakage Tests nance, repair, replacement, and modification work should be prepared before reactor operation is begun.
- 9. Procedures for Performing Maintenance These procedures should include information on areas such as the following:
- a. Maintenance that can affect the performance of safety-related equipment should be properly pre.
(1) Method for obtaining pennission and clear-planned and performed in accordance with written ance for operation personnel to work and for logging such work and procedures, documented instructions, or drawings appropriate to the circumstances. Skills normally (2) Factors to be taken into account, including possessed by qualified maintenance personnel may the necessity for minimizing radiation exposure to not require detailed step-by-step delineation in a pro, workmen, in preparing the detailed work procedures.
cedure. The following types of activities are among those that may not require detailed step-by-step writ-
- 10. Chemical and Radiochemical Control Procedures ten procedures:
Chemical and radiochemical control procedures (1) Gasket Replacement should be written to prescribe the nature and fre-(2) Trouble-Shooting El:ctrical Circuits quency of sampling and analyses, the instructions (3) Changing Chart or Drive Speed Gears or maintaining water quality within prescribed limits, Slide Wires or. Recorders and the limitations on concentrations of agents that -
may cause corrosive attack or fouling of heat-transfer
- b. Preventive maintenance schedules should be surfaces or that may become sources of radiation developed to specify lubrication schedules, inspec-hazards due to activation. These procedures should tions of equipment, replacement of such items as fil-specify laboratory instructions and calibration of lab-ters and strainers, and inspection or replacement of
. oratory equipment. Extreme importance must be parts that have a specific lifetime such as wear rings.
placed on laboratory procedures used to determine 1.33-7
j con' centration and species of radioactivity in liquids sampling, validity of calibration techniques, and ade-j and gases prior to release, including representative quacy of analyses.
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Q.A. Approva :
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10420 mettic boulevatd b
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SHOP ORAWINGS,/
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PROCESS CONTROL SHEET /
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We certify that Support Mark No. _c o-2-org vgf 79ff //je d on our Shipping Notice AUS-88o7#/7bdf has been fabricated in accordance with Gibbs & Hill Specification 2323-MS-468, and conforms to ANSI N45.2, and 10CFR50 Appendix 8.
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