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{{Adams | |||
| number = ML20207N166 | |||
| issue date = 12/31/1986 | |||
| title = Insp Rept 50-443/86-51 on 861028-31.No Violations Noted. Insp Performed to Evaluate Alleged Discrepancies Re as-built Drawings of safety-related Piping & Support Sys | |||
| author name = Manoly K, Strosnider J | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | |||
| addressee name = | |||
| addressee affiliation = | |||
| docket = 05000443 | |||
| license number = | |||
| contact person = | |||
| case reference number = RTR-REGGD-01.029, RTR-REGGD-1.029 | |||
| document report number = 50-443-86-51, IEB-79-14, NUDOCS 8701140025 | |||
| package number = ML20207N160 | |||
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | |||
| page count = 28 | |||
}} | |||
See also: [[see also::IR 05000443/1986051]] | |||
=Text= | |||
{{#Wiki_filter:. | |||
.. | |||
U.S. NUCLEAR REGULATORY COMMISSION | |||
REGION I | |||
Report No. 50-443/86-51 | |||
Docket No. 50-443 | |||
License No. CPPR-135 Category A | |||
Licensee: Public Service of New Hampshire | |||
P.O. Box 330 | |||
Manchester, New Hampshire 03105 | |||
Facility Name: -Seabrcok Station, Unit #1 | |||
Inspection At: Seabrook, New Hampshire | |||
Inspection Conducted: October 28-31, 1986 | |||
"" | |||
Inspectors: | |||
' | |||
# | |||
/YTC/86 | |||
K. Manoly, Lead Reactor Enginelir date | |||
Approved by: ,, /2/J//84 | |||
Strosnider, Chief, Materials and date | |||
yProcessesSection,EB,DRS | |||
, | |||
, o | |||
i | |||
7: | |||
. | |||
Table of Contents | |||
Page | |||
Executive-Summary 1 | |||
1. Persons Contacted 2 | |||
2. Inspection Objective and Scope 2 | |||
3. Allegation Description (RI-86-A-0113) 3 | |||
4. Safety Related Piping Systems As-Built Inspection 4 | |||
4.1 Overview of the Piping As-Built Program 4 | |||
4.2 NRC Walkdown verification of Piping Installations 8 | |||
4.3 Findings 9 | |||
4.4- Conclusion 10 | |||
5. Review of Other Program Activities 11 | |||
5.1 General 11 | |||
5.2 IBuilding Beam Verification Program 11 | |||
5.3 Seismic II/I Interaction Program 12 | |||
5.4 Failure Modes and Effects Analysis (FMEA) Program 13 | |||
5.5 Conclusion 14 | |||
6. Exit Meeting- 14 | |||
Attachments | |||
Appendix I | |||
. | |||
. | |||
EXECUTIVE SUMMARY | |||
Region I performed a special inspection to evaluate alleged discrepancies at | |||
Unit I of Seabrook Station related to the as-built drawings of safety related | |||
piping and support systems. The NRC inspection also covered several other | |||
programmatic activities which included the Building Beam Verification, the | |||
Seismic II/I Interaction and the High/ Moderate Energy Pipe Break Whip and Jet | |||
Impingement Load Verification Programs. | |||
The allegation was made by a former licensee contractor and it primarily dealt | |||
with concerns over the accuracy of the measurements provided on the as-built | |||
drawings and their impact on the adequacy of the piping stress reconciliation | |||
effort and other programs that interfaced with as-built conditions. Details | |||
of the alleged discrepancies in the as-built piping and support drawings and | |||
the NRC evaluation of these discrepancies are provided in Appendix I of this | |||
report. | |||
The processes of piping installation and as-built verification had been | |||
examined and-reviewed by the NRC throughout the construction phase. This | |||
special NRC inspection, in response to the allegation, consisted of: | |||
(1) re-examination of the programs which governed the piping as-built verif- | |||
ication effort (Section 4.1) and the other activities mentioned by the alleger | |||
as potentially deficient (Section 5), and (2) verification of final as-built | |||
piping drawings by performing independent measurements of piping sections | |||
addressed in the allegation and other randomly selected piping systems (Section | |||
4.2). | |||
The NRC review of the programs for piping as-built verification and stress | |||
reconciliation were found to be consistent with accepted industry practice and | |||
were in compliance with NRC requirements set forth in I.E. Bulletin 79-14 for | |||
as-built verification of safety related piping systems. Based on NRC | |||
independent measurements of plant systems, it was found that the final as-built | |||
piping drawings were within acceptable tolerances set by the reconcilation | |||
criteria. The as-built drawings supplied by the alleger were not consistent | |||
with the plant as-built final drawings and apparently were drawings used in | |||
earlier evolutions of as-built verifications. | |||
The approach used by the alleger in performing the interference evaluation | |||
relies on very precise and accurate measurements and a reference system that is | |||
primarily used as a construction aid. It is not necessary, nor is it common | |||
industry practice that measurements of this precision be made to support the | |||
pipe stress reconciliation effort. The use of building reference points | |||
introduces errors because this information is not updated and only utilized to | |||
aid construction forces in locating supports in a general areas. It has no | |||
bearing on final interferences or stress calculations. | |||
Based on the NRC evaluation of licensee programs for the performance of safety | |||
related activities, it was concluded that the programs had met the intent of | |||
the regulations and were substantially in conformance with established industry | |||
standards. The NRC concluded, therefore, that the allegation involving the | |||
adequacy of safety related piping as-built drawings and other safety related | |||
activities at the Seabrook Station is unsubstantiated. No violations were | |||
identified during this inspection. | |||
_ | |||
y | |||
9 | |||
. | |||
2 | |||
1.0 Persons Contacted | |||
1.1 New Hampshire Yankee (NYH) | |||
*J. DeVincentis, Director of Engineering | |||
*T. Pucko, Senior Licensing Engineer | |||
*T. Cizauskas, Lead Mechanical Engineer | |||
*D. Perkins, Licensing Engineer | |||
*S. Sadosky, Manager EAR Program | |||
*W. Sullivan, Senior QA Engineer | |||
1.2 United Engineers and Constructors (UE&C) | |||
8. Huselton, Project Engineering Manager | |||
G. Tuday, FMEA Group Engineer | |||
D. Mehta, Seismic Coordinating Engineer | |||
J. Parisano, Piping Engineer | |||
1.3 CYGNA Energy Services | |||
*P. Baughman, PAPSCOTT Coordinator | |||
1.4 Computerized Interference Elimination (CIE) | |||
S. Mitchell, President | |||
S. Nicholson, General Manager | |||
1.5 U.S. Nuclear Regulatory Commission (NRC) | |||
*A. Cerne, Senior Resident Inspector | |||
*D. Ruscitto, Resident Inspector | |||
D. Haverkamp, Reactor Project Engineer | |||
* Denotes personnel present during the exit meeting on October 31, 1986. | |||
2. Inspection Objective and Scope | |||
The objective of this inspection was to evaluate alleged discrepancies in | |||
, | |||
the as-built drawings of Safety Related (S/R) piping systems qualified by | |||
l | |||
Westinghouse (W) and United Engineers and Constructors (UE&C), and to | |||
assess the potential effect of utilizing these drawings in the performance | |||
of activities involving Building Beam Verification, Seismic II/I Interaction | |||
and Failure Mode and Effects Analysis. To achieve this objective, the | |||
inspection focused on the examination of programs which govern the above | |||
activities and on the performance of independent measurements of piping | |||
sections addressed in the allegation and other randomly selected piping | |||
systems. | |||
l | |||
l | |||
l | |||
- _ _ _ _ _ _ _ _ _ . _ | |||
. . . . _ _ - _ . ,_. - | |||
. | |||
. | |||
3 | |||
3. Allegation Description (RI-86-A-0113) | |||
The Region I (R-I) Office of the NRC was notified by the Region III office | |||
of an allegation involving as-built drawings of safety related piping | |||
systems at the Seabrook station. The Region III staff was informed of the | |||
allegation on August 5, 1986 while conducting an interview with personnel | |||
from Computerized Interference Elimination (CIE), a former contractor to | |||
New Hampshire Yankee (NHY), regarding alleged discrepancies in as-built | |||
drawings of piping systems in Units 1 & 2 of. Byron Station. A copy of the | |||
allegation interview transcript was transmitted to the R-I Office on | |||
September 19, 1986. Two lead Reactor Engineers from the R-I Office | |||
traveled to Redmond, Washington on October 21, 1986 to interview the two | |||
principal allegers from CIE identified above. | |||
The allegers identified certain concerns regarding the existence of | |||
discrepancies in as-built drawings of safety related piping systems | |||
designed by Westinghouse {W) and United Engineers and Constructors (UE&C) | |||
at the Seabrook Station. CIE provided the NRC staff with copies of piping | |||
drawings prepared by W and UE&C relating to the systems involved in the | |||
allegation and six other drawings prepared by CIE depicting the alleged | |||
discrepancies. The discrepancies were noted during the performance of | |||
interference verification utilizing drawings provided by the licensee (NHY) | |||
and information obtained by telephone from NHY, W and UE&C. Five of the | |||
six alleged discrepancies involved walkdown, marked-up drawings by W which | |||
were not approved as final. The allegation primarily dealt with concerns | |||
over the accuracy of the measurements provided on the drawings and the | |||
impact on the adequacy of the licensee's pipe stress reconciliation efforts. | |||
- | |||
It also referenced other design activities which could potentially be | |||
" | |||
affected as a result of using input data from as-built drawings containing | |||
discrepancies. These activities included Building Beam Verifications, | |||
Seismic II/I Interaction, and High/ Moderate Energy Pipe Break Whip and Jet | |||
Impingement Load Verification Programs. | |||
The alleged discrepancies in the as-built piping drawings involved apparent | |||
offsets in the location of certain piping sections or supports. The offsets | |||
were noted as the alleger attempted to trace. piping system configurations | |||
and related supports from information provided on drawings of walkdown | |||
isometerics, penetration sleeve details, building steel floor layout, | |||
concrete wall penetration location, and pipe supports detail / reference | |||
location. The magnitude of the maximum alleged dimensional discrepancy | |||
was approximately I'-6". | |||
' | |||
The specific discrepancies, according to the alleger, are summarized in | |||
Appendix I of this report. | |||
.- | |||
e | |||
4 | |||
4. Safety Related Piping Systems As-Built Inspection | |||
4.1 Overview of the Piping As-Built Program | |||
The scope and controlling procedures for the as-built program of Safety | |||
Related (S/R) piping systems differed according to the organization | |||
responsible for the erection or the design and reconciliation of com- | |||
pleted installations. Though the majority of S/R piping and support | |||
installations (except for the primary coolant loop) were fabricated | |||
by DRAVO and erected by Pullman Power (P-H), the responsibility for | |||
the design and reconciliation of ASME Class I piping was that of W | |||
and for Class II, III and ANSI 831 piping was UE&C. As-built verifi- | |||
cation of completed piping installation was conducted twice, first by | |||
P-H as part of the ASME code "NA" certification prior to turnover and | |||
second, by W and UE&C in support of the stress reconciliation effort | |||
of their respective piping. | |||
The inspector conducted interviews with cognizant licensee representa- | |||
tives and reviewed procedures (Attachment 1) established by Westinghouse | |||
(W) and UE&C which governed some of the activities performed by the | |||
Piping and Pipe Support Closeout Task Team (PAPSCOTT). These activities | |||
included the as-constructed walkdowns and the stress analysis reconcil- | |||
iation and pipe support verification tasks in support of the ASME N-5 | |||
certification program. | |||
The flow chart in figure 4-1 depicts the sequence of activities | |||
involved in the ASME completion program for piping systems from the | |||
design phase through code certification. The numbers in the flow | |||
chart blocks identify the sequence of certain activities performed by | |||
the engineering / design and installing organizations. The as-engineered | |||
piping was typically shown on design isometrics by W or UE&C (block | |||
1). The desigr. isometrics were transmitted to the fabricator (DRAVO) | |||
for preparation of piping spool drawings. These drawings were used | |||
by the installer (P-H) for the preparation of erection drawings and | |||
subsequent piping erection (block 2). Field verification of piping | |||
and related components installed in accordance with ASME Section III | |||
was performed by the installer prior to turnover to satisfy code | |||
certification requirements. Data verified during the installer's | |||
walkdown were either incorporated in revised erection drawings or | |||
red-lined on current isometrics (block 3). Walkdown verification of | |||
as-built piping installations was subsequently conducted by the | |||
engineering / design organization for the purpose of piping stress | |||
reconcilation. Though some of the verification attributes were | |||
common to both walkdowns, the piping data verified during the recon- | |||
cilation effort were pertinent to piping stress analysis and code | |||
acceptance limits. Results of the latter walkdown were recorded on | |||
marked up isometrics (Block 4). These isometrics were considered | |||
final when the marked walkdown drawings were signed as approved, as | |||
in the case of W drawings, or when stamped "As-Constructed", as in | |||
the case of UE&C drawings. | |||
. . . _ - - - | |||
.g'- | |||
% | |||
. | |||
' | |||
5 | |||
- The significant features.cf the piping as-built program which related | |||
to the allegation concerns are presented below. | |||
I. As-Built Walkdown Prior to Turnover- | |||
-- | |||
Interface activities between P-H, UE&C and the startup test | |||
department, relative.to the release and turnover of systems | |||
were described in P-H Procedure X-23. | |||
-- | |||
Documentation of field verifications, final inspection and | |||
final _ review of ASME III piping was governed by P-H Procedure | |||
X-4. | |||
--- | |||
The walkdown was conducted by P-H field engineering in. accord- | |||
ance with walkdown_ implementing Procedure No. X-30 for field | |||
verification and recording of piping linear measurements | |||
and elevations. | |||
-- | |||
Field verification of supports was conducted to P-H Procedure | |||
JS-IX-6. | |||
-- | |||
Walkdown packages including as-built isometric drawings and | |||
walkdown verification forms were transmitted to P-H/QC for. | |||
_ performance of final piping and support inspections. | |||
~ | |||
-- | |||
Walkdown packages were transmitted to P-H/QA for review of | |||
completeness prior to the sign off on ASME Code "NA" certi- | |||
fication. | |||
-- | |||
Data recorded during the as-built walkdown were either_incor- | |||
porated in revised erection isometric drawings (prior to mid- | |||
1984) or red-lined on current erection isometrics (after mid- | |||
1984). | |||
II. ' Piping Qualified by W | |||
, | |||
l | |||
-- | |||
W generated the piping design isometrics using original UE&C | |||
j isometrics, and performed the piping stress analyses of record, | |||
f -- | |||
As-built piping walkdowns were performed by teams including | |||
engineering and surveying personnel to' record piping config- | |||
i uration on the design drawings in accordance with Procedure | |||
l- SSP-1. Angular measurements were recorded at elbows and pipei | |||
l bends, though no specific tolerance was provided in procedure | |||
! SSP-1. A tolerance of 5 degrees in angular measurements was | |||
: noted in a correspondence between W and NHY. | |||
f | |||
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6 | |||
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ic | |||
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. -- | |||
.. - _ _ _ _ - _ - _ | |||
.- - _ . - -- _ | |||
. | |||
. | |||
7 | |||
-- | |||
Marked-up walkdown drawings were reviewed against change | |||
documents and other design information for evaluation of | |||
discrepancies identified during the walkdown process.before | |||
final approval of the drawing. | |||
-- | |||
Reconciliation of as-built installations addressed five | |||
categories involving piping configuration, pipe supports, | |||
pipe properties, loading conditions and interferences. | |||
-- | |||
The acceptance criteria for the reconciliation effort were | |||
stated in Procedure SSP-2. | |||
-- | |||
Piping neasurements which exceeded the reconciliation accept- | |||
ance criteria were reconciled either by hand calculations or | |||
computer re-analysis, and noted on final analysis isometric | |||
drawings. However, measurements which fell within the accept- | |||
ance criteria were not noted on these drawings. | |||
-- | |||
Final piping as-built packages consisted of approved walkdown | |||
isometric drawings containing three signatures, final analysis | |||
isometric and stress analysis report. | |||
III. Piping Qualified by UE&C | |||
-- | |||
UE&C generated piping isometrics which were used by | |||
Pullman Power for the preparation of installation drawings. | |||
-- | |||
Location of piping supports during the installation phase | |||
was based on measurements provided on each support drawing | |||
from nearby building elements such as walls, beams, columns, | |||
etc. These dimensions were provided in addition to location | |||
plan measurements which were intended for reference purpose | |||
only. | |||
' | |||
-- | |||
UE&C utilized Pullman drawings and related ECA's and NCR's | |||
, to update the piping isometrics. | |||
-- | |||
The elements of the piping as-constructed walkdown data | |||
collection were described in procedure FAEP-1. Design | |||
drawings and checklists were used to record walkdown data | |||
which include: (1) location of pipe supports relative to the | |||
piping; (2) location of floor / wall sleeve and gaps relative | |||
to piping; (3) pipe support function; (4) pipe support gaps; | |||
(5) location / orientation of welded attachments; and (6) build- | |||
ing location dimensions. | |||
-- | |||
Additional requirement regarding the walkdown data collection | |||
and the accuracy of measurements was provided in Technical | |||
Procedure TP-26. | |||
1 | |||
-_ - . .-- | |||
_ , . - . _ _ . . _ _ .- ,- , | |||
F | |||
. | |||
. | |||
8 | |||
-- | |||
Verification of piping as-built angle data was not addressed | |||
in the walkdown procedures. The rationale for not performing | |||
angular measurements during this phase included consideration | |||
of very stringent tolerances in the location of end components | |||
and the fabrication and erection of pipe support components | |||
and piping spools. Variations in piping segments length due | |||
to cutting or addition of sections during fit-up of spool | |||
pieces were verified and reconciled during the walkdown effort. | |||
Results of a confirmatory walkdown conducted in 1983-1984 were | |||
provided in support of the above rationale. The walkdown | |||
involved approximately 500 drawings for verification of piping | |||
bend angles as well as end-components and support locations. | |||
Evaluation of the results from 130 drawings indicated that | |||
angles were within 5 tolerance of drawings or ECA's. | |||
-- | |||
Dimensions verified in the walkdown effort were circled on | |||
the final as-constructed drawings. | |||
-- | |||
The evaluation criteria and acceptable tolerances used for | |||
the reconciliation of as-constructed installation were stated | |||
in Appendix "C" of Procedure PGL-7. The tolerances were | |||
consistent with the recommendation in a technical position | |||
paper on piping installation tolerances sponsored by the | |||
PVRC technical committee on piping systems and published in | |||
Bulletin 316 of the Welding Research Council. | |||
-- | |||
Firal as-built packages consisted of isometric "As-Con- | |||
structed" drawings reflecting walkdown measurements, final | |||
analysis isometrics and stress analysis reports. | |||
4.2 NRC Walkdown Verification of Piping Installations | |||
A physical inspection was conducted, by the NRC inspector of piping | |||
installations referenced in the allegation and other randomly selected | |||
systems. The inspection included several piping segments of the RHR | |||
system inside and outside the containment (by W and UE&C) in addition | |||
to segments of the piping system from the accumulators (No.1 & 2). | |||
The inspection utilized W stress isometric and UE&C as-constructed | |||
drawings. Piping segments and drawings used in this effort are | |||
identified in Attachment 2 to this report. | |||
The purpose of this effort was to examine the conformance between | |||
installed piping systems and the information recorded on walkdown and | |||
analysis isometric drawings. Though the processes of piping installa- | |||
tion and as-built verification were examined and reviewed by the NRC | |||
throughout the construction phase until completion, this effort was | |||
undertaken primarily to assess the specific discrepancies identified | |||
in the allegation and to further examine piping installations in | |||
general, for potential non-conformances of a type which would invalidate | |||
the piping stress reconciliation effort. Examples of previous NRC | |||
inspections of piping as-built verification inspections can be found | |||
in Inspection Report Nos. 50-443/85-09, 85-15, 86-14, 86-43 and 86-46. | |||
. | |||
. | |||
9 | |||
The verification walkdown included visual inspection and performance | |||
of independent measurement of selected piping installations. The | |||
attributes of the inspection included the following: | |||
-- | |||
Checking actual configurations against piping drawings. | |||
-- | |||
Performing linear measurements between components and supports | |||
along the piping using a tape measure. | |||
-- | |||
Checking piping angles either visually or by trigonometric | |||
correlation of linear measurements on piping legs where possible. | |||
-- | |||
Checking valve types and tagging. | |||
-- | |||
Checking support types to verify restraint function. | |||
-- | |||
Checking clearances between piping and supports where required. | |||
A total of 153 linear measurements were verified during the piping | |||
walkdown, of which 98 were performed on W piping and 55 on UE&C | |||
piping. It should be noted that the majority of piping inspected | |||
was insulated; thus, measurements which were difficult to perform | |||
were considered acceptable if within 2" of recorded dimensions. | |||
Measurements performed on W piping which exceeded the walkdown | |||
acceptance tolerance were later compared against recorded measure- | |||
ments on walkdown isometric drawings. | |||
4.3 Findings | |||
The following findings are based on the NRC review of the piping | |||
as-built program, walkdown verification of selected piping installa- | |||
tions, and examination of alleged discrepancies. | |||
1. The procedures established for the performance of piping as-built | |||
walkdown verification and stress reconciliation efforts were | |||
found to be consistent with accepted industry practice. Further- | |||
more, the licensee's approach to the as-built process met the | |||
requirements and intent of the NRC's I.E. Bulletin 79-14 in that | |||
it provided the needed verification of the attributes and dimen- | |||
sions, within acceptable tolerances, which define the relative | |||
' | |||
configuration of piping and are considered critical to design | |||
and the validity of the piping stress analysis. Verification of | |||
reference dimensions which affect the global position, relative | |||
to the building structure, of piping and supports in three | |||
dimensional space was not generally included in the as-built | |||
program and is not required to be included. Verification of | |||
dimensions between piping systems and building structures is not | |||
required for stress reconcilation since the piping stresses are | |||
determined by the piping system geometry not the piping to | |||
building structure dimensions. | |||
. - _ . _ . _ . _ __ _ __ | |||
. | |||
. | |||
10 | |||
2. The alleged discrepandes in as-built drawings of safety related | |||
piping systems were for the most part incorrect due to: | |||
a) use of W walkdown drawings which were not final, | |||
b) introduction of erroneous values of piping dimensions at | |||
flued head sleeve anchors in the attempt to correlate dimen- | |||
sional information from sleeve detail drawings by UE&C and | |||
walkdown drawings by W (apparently the result of miscommuni- | |||
cation between the alleger and field personnel), | |||
c) use by the alleger of several values beyond their intended | |||
accuracy, particularly with regard to support location | |||
reference dimensions and location of both building steel | |||
members and wall penetrations, and | |||
d) reliance by the alleger on exact values to be recorded on | |||
piping walkdown drawings while ignoring linear and angular | |||
tolerances which were inherent in the field walkdown process. | |||
Detailed evaluation of the specific alleged discrepancies is | |||
provided in Appendix I of this report. | |||
3. Minor dimensional discrepancies were noted between linear measure- | |||
ments performed during the NRC piping walkdown and dimensions | |||
recorded on the walkdown drawings. A total of eleven (11) discre- | |||
pancies was found, of which eight (8) were within 3" of the walk- | |||
down drawings and the remaining three within 3.75", 5.5" and 6" | |||
respectively. It should be noted, however, that three of the | |||
dimensions with discrepancies involved measurements which were | |||
difficult to perform due to insulation and inaccessability of the | |||
piping system. Furthermore, in all of the dimensions involving | |||
discrepancies, the difference between the design and measured | |||
dimensions were well within the acceptable tolerance set by the | |||
reconciliation criteria. Thus, a re-analysis of associated piping | |||
would not have been required. | |||
4.4 Conclusion | |||
The inspector concluded that the program for the as-built and reconcil- | |||
iation process of safety related piping and support systems, qualified | |||
by W and UE&C at the Seabrook Station, were consistent with accepted | |||
industry practice and no items of non-compliance were identified with | |||
regard to NRC requirements set forth in I.E. Bulletin 79-14. Further, | |||
upon review of the alleged discrepancies and performance of walkdown | |||
verification of completed piping installations, it was apparent that | |||
the as-built drawings had reasonably depicted the piping configurations | |||
as required for performing the stress reconciliation effort. It was | |||
also concluded that the approach utilized by the alleger in performing | |||
the interference verification relies on very precise and accurate | |||
. | |||
. | |||
11 | |||
measurements of piping components and building elements. Some of these | |||
measurements are recorded with tolerances (as in the case of piping and | |||
support systems), and the remaining are not typically verified in the | |||
as-built walkdown (as in the case of support reference dimensions, | |||
penetration and building steel locations, etc.). It is not necessary, | |||
nor is it common industry practice, that these precise measurements be | |||
made to support the pipe stress reconciliation effort. | |||
Based on the above, it is concluded that the allegation involving the | |||
adequacy of as-built safety related piping systems at the Seabrook | |||
Station is unsubstantiated. | |||
5.0 Review of Other Programmatic Activities | |||
5.1 Gereral | |||
The NRC review included an assessment of several other programmatic | |||
activities performed by the licensee which were addressed by the | |||
alleger as potentially deficient due to the alleged dimensional | |||
discrepancies. The programs covered in this effort included the Beam | |||
Verification, the Seismic II/I Interaction, and the Failure Mode and | |||
Effects Analysis Programs. The review focused primarily on the scope | |||
and implementation of these programs to verify their conformance to | |||
acceptable industry standards and their compliance to NRC regulations. | |||
The review also covered the interface between these activities and | |||
the piping as-built verification effort to assess the alleged potential | |||
for ineffective evaluations as a result of using the piping as-built | |||
drawings in the performance of these programs. | |||
5.2 Building Beam Verification Program | |||
The purpose of this effort was to verify that the design of category | |||
I structural steel, which was based on assumed loads, was adequate | |||
for final as built system loads. The program was managed by UE&C, | |||
and described in technical procedure TP-16. It was initiated in 1983 | |||
with the establishment of a data base of all appropriate loads required | |||
for the beam verification effort. The original design was based on | |||
consideration of assumed uniform loads in addition to known heavy | |||
attachment and equipment loads. During this design phase, the intent | |||
was to maintain flexural beam stresses below 18 ksi. | |||
The beam verification program was carried out in two phases. The | |||
scope of the first phase included an initial verification of framing | |||
systems using discrete design loads and locations for major attach- | |||
ments, such as large bore pipe supports and equipment, and appropriate | |||
(envelope) uniform loads for attachment of cable tray, conduit, I&C, | |||
and small bon pipes. Structural weights and live operational loads | |||
were also considered in this phase. The magnitudes of selected | |||
envelope uniform loads in different plant zones were based on walk- | |||
downs performed in 1984. | |||
. | |||
. | |||
12 | |||
Beams evaluated in the first phase whose flexural stresses fell | |||
between 18 and 22 ksi were designated as heavily loaded beams. Those | |||
which exceeded 22 ksi were designated as critically loaded beams and | |||
painted with an orange paint. The painting was intended to prevent | |||
any attachments to these beams without prior approval from the | |||
structural group. Re-evaluation of critically loaded beams was | |||
performed using more refined analytical techniques and actual attach- | |||
ment loads in lieu of assumed conservative uniform loads. | |||
The second phase in the verification program involved the incorporation | |||
of PAPSCOTT reconciled piping support attachment loads. The following | |||
three categories of beams were considered in this re-evaluation: | |||
-- | |||
Typical beams (stressed below 18 ksi) were re-analyzed if the | |||
magnitude of uniform loads had increased significantly or if | |||
attachments of piping 4" in diameter or larger were added. | |||
-- | |||
Heavily loaded beams were re-evaluated for any additional loads | |||
to ensure that flexural stresses were below 22 ksi. | |||
-- | |||
Critically loaded beams were re-evaluated if the applied loads | |||
from the first phase had increased. A walkdown was typically | |||
performed to verify the as-built geometry, loading and boundary | |||
conditions for these beams. | |||
-This second phase of the beam verification program was completed in | |||
July of 1986. | |||
5.3 Seismic II/I Interaction Program | |||
The program, described in Technical Procedure TP-4 (Review of Non-Safety | |||
Related Equipment, Systems, and Supports located in Safety Related | |||
Buildings) was conducted by UE&C to meet the requirements of Regulatory | |||
Guide 1.29, Position C2. The Regulatory Positions was implemented by | |||
, | |||
either of the *-llowing approaches: | |||
1 | |||
(a) Providing seismic supports to non-safety related systems and sup- | |||
ports (such as piping, ducts, cable trays, conduits, bus ducts, | |||
and I & C trays and tubing) located in safety related baildings | |||
to prevent their failure and damaging of safety related systems | |||
and components during a seismic event. | |||
(b) For items which were not seismically supported, Failure Modes | |||
and Effects Analysis (FMEA) was performed to assure that they | |||
were isolated by their location and their postulated failure | |||
would not impact on safety related components during a seismic | |||
event. | |||
' | |||
. | |||
._- . _ - . . - . | |||
. | |||
. | |||
13 | |||
-The procedure (TP-4) provided a tabulation of non-safety related items | |||
which were installed in safety related buildings. These items (generally | |||
considered large equipment) included tanks, instrument racks, seismic | |||
*ccceders, cooling units, dampers, cooler fans, louvers, sump pumps, | |||
chtlier pumps, cabinets, unit heaters, radiation monitors, etc. This | |||
equipment was listed by the building in which it was located and was | |||
identified by its classification, tag number, type of anchorage and | |||
relative location to other safety related equipment. Support for non- | |||
safety related and seismically mounted equipment identified in TP-4 was | |||
provided in special detailed drawings by the manufacturer or UE&C. | |||
D.her small non-safety related items such as instruments, wall mounted | |||
electrical boxes, switches, etc. were not addressed in procedure TP-4. | |||
These were seismically mounted in accordance with typical notes and | |||
details for I&C and conduit support drawings. | |||
A two phase confirmatory field walkdown was instituted in early 1986 for | |||
al) non-isolated, seismically anchored and all isolated, non-seismically | |||
anchored equipment listed in TP-4. The walkdown was completed in the | |||
Diesel Generator, Fuel Storage, Service Water Pump House and Service | |||
Water Cooling Tower. This effort was discontinued, however in other | |||
safety related areas due to lack of findings. | |||
Licensee evaluation of the seismic II/I interaction was substantially | |||
complete except for a walkdown which is currently being performed of all | |||
hose reels and fire extinguishers in safety related areas for isolation | |||
and requirement for seismic mounting. | |||
5.4 Failure Modes and Effects Analysis (FMEA) Program | |||
This FMEA program was initiated by the licensee to address the require- | |||
ments of 10 CFR 50, Appendix A, General Design Criteria 4 which requires | |||
that structures, systems, and components important to safety be designed | |||
to accommodate the effects of postulated accidents, including appropriate | |||
protection against the dynamic and environmental effects of postulated | |||
pipe ruptures. The program provided evaluation of pipe whip, jet | |||
impingement, and flooding effects on safety-related plant systems, | |||
structures and components. The evaluation was documented in eighty-three | |||
(83) zone reports which contained the information required to evaluate | |||
the consequences of piping failures within the zone on essential plant | |||
systems and components. | |||
The program was managed by UE&C and was performed in accordance with | |||
Technical Procedure TP-3. The procedure adopted the guidance for | |||
postulated rupture locations, types and sizes presented in the Standard | |||
Review Plan (NUREG-800), Sections 3.6.1 and 3.6.2. The criteria estab- | |||
lished the specific rupture conditions to be evaluated including the | |||
consequential effects of the ruptures. | |||
i | |||
I | |||
, | |||
I | |||
< | |||
~ | |||
. | |||
14 | |||
The evaluation effort was accomplished in two phases. The first phase | |||
(1982-1985) was performed using plant design drawings, such as struc- | |||
tural, general arrangement, piping, HVAC, etc., for detection of targets | |||
to be evaluated. The second phase consisted of plant walkdowns to verify | |||
actual as-built conditions of safety-related systems and components | |||
evaluated in the first phase, and to identify other safety related | |||
systems, components and field run commodities which were not previously | |||
addressed. The inspector was informed that the Seabrook scale model | |||
was not utilized in the conduction of either phase. Prior to performing | |||
the plant walkdown, an evaluation was performed of as-constructed piping | |||
drawings by W and UE&C.to identify systems which had changed in configur- | |||
ation to assess the likelihood of revised postulated break locations and | |||
potential targets. Criteria for acceptability of interaction involved | |||
considerations of system operability and/or structural functionality. | |||
The second phase of the FMEA activities was completed in April, 1986. | |||
5.5 Conclusion | |||
Based on the NRC evaluation of licensee programs for the performance | |||
of safety related activities addressed above, it was concluded that the | |||
programs had met the intent of the regulations and were substantially | |||
in conformance with established industry standards. Further, upon | |||
review of the interfaces between the piping as-built program and the | |||
Beam Verification and Failure Mode and Effects Analysis programs, it | |||
was concluded that they were adequate for performing these activities. | |||
Based on the above, it is concluded that the allegation involving | |||
the adequacy of these safety related activities at the Seabrook | |||
Station is unsubstantiated. | |||
6. Exit Meeting | |||
The inspector met with licensee representatives (denoted in paragraph 1) | |||
at-the conclusion of the inspection on October 31, 1986. The inspector | |||
summarized the purpose and the scope of the inspection arid the^ findings. | |||
At no time during this inspection was written material provided by the | |||
inspector to the licensee. | |||
. | |||
. | |||
ATTACHMENT 1 | |||
DOCUMENTS REVIEWED | |||
The following documents were reviewed, in part, during the course of | |||
inspection: | |||
* | |||
Procedure No. X-30 for field verification of piping by Pullman Power | |||
* Procedure No. X-4 for field inspection by Pullman Power | |||
* Procedure No. X-23 for Turnover by Pullman Power | |||
* | |||
Procedure No. PGL-7 for AMSE and NNS-IA Piping and Pipe Support | |||
Reconciliation Program by UE&C | |||
* Position Paper on Acceptance Criteria for Piping Installation by UE&C | |||
* | |||
Technical Procedure No. TP-26 for As-Constructued Requirements of Piping | |||
Systems by UE&C | |||
* | |||
Procedure No. FAEP-1 for ASME Field Data Completion Program by UE&C | |||
* | |||
Technical Procedure No. TP-33 for "As-Constructed" Verification Program | |||
for ASME Piping System Installed by UE&C | |||
* Procedure No. SSP-1 for As-Built Reconciliation Walkdown Guidelines by W | |||
* | |||
Procedure No. SSP-2 for Review of the As-Built Condition of Westinghouse | |||
Analyzed Auxiliary Lines | |||
* | |||
Quality Control Procedure No. QCP-17-5 for N-5 Data Report by UE&C | |||
* | |||
Specification No. 9763-006-248-51 for Assembly and Erection of Piping and | |||
Mechanical Equipment by UE&C | |||
* | |||
Procedure No. JS-1X-6 for Installation and Inspection of ASME III Pipe | |||
Supports by Pullman Power | |||
* | |||
Procedure No. TP-3 for Conducting Failure Modes and Effects Analysis | |||
(FMEA) Piping Failure by UE&C | |||
* | |||
Procedure No. TP-4 for Review of Non-Safety Related Equipment, Systems | |||
and Supports located in Safety Related Buildings by UE&C | |||
* | |||
Technical Procedure No. TP-16 for Beam Verification Program | |||
l | |||
l | |||
-. . | |||
.-- - _ . _ _ _ _ - _ _ | |||
. | |||
. | |||
ATTACHMENT 2 | |||
Piping Qualified No. of Description of Piping | |||
Line No. By Measure- Section Verified | |||
Drawing No. ments | |||
RHR1-W0013 (Sh.1) RC-13-13-601-12" W 10 Between penetration and | |||
sleeve No. 13 A | |||
RHR1-W0013 (Sh.2) 180-1-2501-8" W 11 Between line 160 and | |||
penetration No. 34 | |||
RH4-W-0058(Sh.1) 58-13-601-12" W 12 Between penetration X-10 | |||
and 10-lh" horizontal | |||
run beyond hanger No. | |||
58-SG-07 | |||
RH4-W-0058(Sh.2) RH-160-3-2501-12" W 17 Between penetration X-13 | |||
& 160-4-2501-8" and 1-5" horizontal run | |||
beyond hanger No. | |||
160-SG-05 | |||
ACC1-W0155 (Sh.1) SI-201-1-601-10" W 26 Between ACC. Tank.9A | |||
and 2'-10 " horizontal | |||
run beyond hanger No. | |||
201-RM-15 | |||
ACC2-W0162 (Sh.1) SI-201-1-601-10" W | |||
- | |||
22 Between ACC. Tank 9B : | |||
and I'-9" horizontal | |||
run beyond hanger No. | |||
202-RM-09 | |||
F-800160-542.01 160-1-601-8" U&EC 35 Between penetration | |||
X-13 and 7'-0" | |||
horizontal run beyond | |||
sleeve No. 1558 | |||
D-800014-491.70 RC-14-1-601-3" U&EC 20 Between line No. | |||
l RC-13-2-601-12" and | |||
' | |||
10 " horizontal run | |||
before hanger No. | |||
' | |||
14-SG-8 | |||
l | |||
l | |||
.. . . - _ _ - . . .. . ___. _ _ , . | |||
_ _ ._ | |||
. | |||
. | |||
Appendix I | |||
Details of the alleged discrepancies in as-built piping drawings are given below. | |||
For each of the six descrepancies, the description, according to the alleger's | |||
drawings, is followed by the results of the NRC evaluation. Simplified | |||
figures, projected from the allegers drawings, are included to illustrate the | |||
configuration and geometry of piping, supports and building sections involved. | |||
a. Descrepancy Drawing No. 53-A | |||
Details: W piping No. RC-13-13-601-12" shown on sheet 1 of Dwg. No. | |||
RHR1-W0013: The piping runs from penetration No. X-9 to sleeve No. 13A | |||
(incorrectly referenced as sleeve No. 33). The piping was shown by the | |||
allegers analysis to be interfering with the concrete wall as it penetrates | |||
sleeve No. 13A. An offset of approximately 4" was shown between the piping | |||
and sleeve centerlines. (See attached Dwg. No. 1) | |||
NRC Evaluation: The l'-0" dimension between the inside face of the con- | |||
tainment at penetration No. X-9 and the weld line is irrelevant. The 12'-8 | |||
3/4" starting dimension shown on the run of piping (No. RC-13-13-601-12") | |||
from the weld line to the bend is incorrect. The measurement should be from | |||
the penetration guide at the face of the lug. The incorrect assumption | |||
introduced-an additional 6 3/4" to the piping run length towards the east | |||
direction. Further, the opening for sleeve No. 13A was shown to be approxi- | |||
mately 16" in diameter, whereas it measured approximately 23". Correction | |||
of both errors in the alleger's analysis would eliminate the discrepancy ana | |||
allow the pipe to pass through the sleeve with no interference. | |||
b. Discrepancy Drawing No. 53-B | |||
Details: UE&C piping No. RC-14-2-A7-4" and support No. 14-SG-7 shown on | |||
Dwg. No. D-800014-491-70: The piping branches off W piping header No. | |||
RC-13-13-601-12" identified in (a) above. The piping at the location of | |||
the support was shown to be offset by approximately 9". (See attached- | |||
Dwg No. 2) | |||
! | |||
NRC Evaluation: Three dimensional errors were noted. The first involved | |||
~ | |||
the incorrect point of line No. RC-13-13-601-12" from penetration No. X-9, | |||
identified in "a" above, which resulted in the introduction of a 6 3/4" error. | |||
The second and third involved two dimensions on east-west runs of piping | |||
No. RC-14-2-A7-4" by UE&C. The dimensions which were shown on Dwg. No. 538 | |||
as 2-6 1/2" and 2-11" were recorded on UE&C "as constructed" drawing No. | |||
; D-800014-491.70 and verified by the NRC walkdown as 2'-6" and 2'-91/4". | |||
These two errors introduced an additional 2 1/4" in the east direction. | |||
l The three errors collectively resulted in the alleged offset of 9" between | |||
the piping and the support. | |||
, | |||
j | |||
l | |||
. - | |||
. . _ , -_ | |||
_- | |||
. | |||
. | |||
Appendix I 2 | |||
c. Discrepancy Drawing No. 53-C | |||
Detail: Two related discrepancies in: (1) W piping No. RH-160-3-2501-12" | |||
shown on sheet 2 of Dwg. No. RHR4-W0058; (27 W piping No. RH-180-1-2501-8" | |||
shown on sheet 2 of Dwg. No. RHR-1-W0013; (3) UE&C piping No. RH-182-1-2501-3/4" | |||
shown on Dwg. No. 800182-S43.00; and (4) UE&C piping No. RH-181-1-2501-3/4" | |||
shown on Dwg. No. 800181-543.01. The four piping lines e.re connected in a | |||
closed loop in the same sequence listed above where line No. 181 connects | |||
back to the main header No. 160. The first discrepancy involved an offset | |||
in the connection between lines No. 181 & 160 of approximately 10". The | |||
second discrepancy involved an offset in the location of support No. 180-SG-4 | |||
on line No. 180 from its designated location on the building steel. (See | |||
attached Dwg No. 3) | |||
NRC Evaluation: The dimension 6'-8 9/16" between-the elbow on line No. | |||
RH-180-1-2501-8" and the junction to branch line No. RH-182-1-2501-3/4" is | |||
incorrect. The dimension was shown on W stress isometric as 7'-7 7/8" and | |||
- | |||
was measured during the NRC walkdown as 7'-81/4". The alleged offset | |||
discrepancy of 10" could be substantially eleminated if the difference | |||
between the correct and the alleged dimensions is multiplied by the cosine | |||
of the angle between the line and the east-west axis (20 ). The alleged | |||
offset in the location of support No. 180-SG-4 on line no. 180 could be | |||
substantially reduced if the 24'-3 7/8" dimension on line no. RH-160-3-2501-12" | |||
is corrected to 25'-10", and the starting point of the same line from the | |||
lug at penetration no. X-13 to the elbow is corrected to 2'-91/2". This | |||
is addressed further in the next alleged discrepancy. Further, it is | |||
significant that the second alleged discrepancy was based on correlation | |||
of piping as-built verification measurements with dimensions obtained from | |||
the pipe support reference location and the building steel layout drawings. | |||
Since neither the support reference nor the building steel location | |||
dimension was verified (or required to be verified), the alleged discrepancy | |||
is deemed erroneous. | |||
d. Discrepancy Drawing No. 53D | |||
Details: W piping No. RH-160-3-2501-12" shown on sheet 2 of Dwg. No. | |||
RHR4-W0058. Two discrepancies were noted: The first involved an offset | |||
in the location of supports No. 160-SG-5 and 160-RM-6 on the above line | |||
from their designated location on the location plan of the respective | |||
support drawings. The offset was approximately 18" on both supports. The | |||
second discrepancy involved an offset in the connection of line No. | |||
250-4-2501-2" to line No. 160-5-2501-8". The offset was shown as 11 13/16" | |||
in the east-west direction and l'-3 7/8" in the north-south direction. | |||
(See attached Dwg No. 4) | |||
-_. _ _ - - - - - . _ _ - - - - | |||
. | |||
a | |||
Appendix I 3 | |||
NRC Evaluation: The alleged offsets in both support locations and the branch | |||
line connection were caused by two dimensional discrepancies on the piping | |||
run in addition to the use of reference centerline dimensions from structural | |||
drawings in locating pipe support attachments. The starting 2'-9 1/2" dimen- | |||
sion of piping No. RH-160-3-2501-12" from penetration No. X-13 to the first | |||
elbow should be measured from the face of the lug rather than from the piping- | |||
to-sleeve weld line as shown on Dwg. No. 53-D. The other dimensional discrep- | |||
ancy involved the length of the piping run from the elbow (near penetration | |||
X-13) to the first piping bend. The dimension was noted as 24'-3 7/8" on Dwg. | |||
No. 53-D and on the W preliminary walkdown drawing. The correct dimension | |||
was shown on the final W isometric drawing as 25'-10". Since the dimensional | |||
error in the W drawing involved a walkdown drawing which was still in process, | |||
the inspector could not determine with certainty whether the internal checks | |||
by W had independently identified the error. Nevertheless, the alleged off- | |||
sets can be substantially eliminated when the above dimensional corrections | |||
are incorporated. | |||
e. Discrepancy Drawing No. 53-E | |||
Details: UE&C piping No. 160-1-601-8" shown on Dwg. No. F-800160-542.01. | |||
The piping is routed through six penetrations. The discrepancy involved an | |||
offset between the piping and penetration No. 1416 by approximately 3.5" | |||
towards the north direction. It also involved an offset between the same | |||
piping and penetration No. 1584 by approximately 3.5" towards the south' | |||
direction. (See attached Dwg No. 5) | |||
NRC Evaluation: The alleged discrepancy was determined to be erroneous | |||
because it was based on inherently incorrect assumptions and misunderstand- | |||
ings of the as-built process. The relative locations and orientations of | |||
the six penetrations involved in this discrepancy were neither verified | |||
with respect to each other nor with respect to a fixed reference point, | |||
and are not required to be, during the as-built process. In addition, | |||
penetration centerlines were not necessarily parallel to, or concentric | |||
with, centerlines of piping which passe through these penetrations. Any | |||
possible angularity, within the 5 tolerance, between the centerline of | |||
the piping run (No. 160-1-601-8") and the penetrations involved will | |||
eliminate this apparent discrepancy. % NRC inspector's walkdown of the | |||
piping involved between penetrations Ro. !-13 and 1558 confirmed the | |||
adequacy of measurements on the ''dv >nr * ucted" drawing by UE&C within | |||
specified tolerances. | |||
f. Discrepancy Drawing No. 53-F | |||
Details: Configuration of W piping No. RC-13-13-601-12" from penetration | |||
No. X-9 or sheet 1 of Dwg. No. RHR-1-W0013 (incorrectly identified as piping | |||
No. RC-13-1-2501-12"): The piping configuration was shown twice using dimen- | |||
sions from W drawing above, and Pullman Power erection Dwg. No. RC-13-06. | |||
The two configurations were offset by approximately 5'-0" in the east-west | |||
direction primarily due to the difference in length of the piping run from | |||
the penetration. The other discrepancy in the same drawing depicted the | |||
distance between the two legs of a U-bend as 2'-9" according to W drawing | |||
and as 3'-6" according to Pullman drawing. | |||
. | |||
I | |||
' | |||
, . | |||
Appendix I 4 | |||
NRC Evaluation: The dimension of piping No. RC-13-13-601-12" from penetra- | |||
tion No. X-9 to the first bend was consistent between W and Pullman erection | |||
drawings, contrary to the 5-0" offset shown on Dwg. 53-F between the two | |||
layouts. Further, the apparent discrepancy in the piping dimension, between | |||
the two legs of the U-bend, was resolved since it was noted and verified as | |||
3-6" on both W final isometric and Pullman erection drawings. | |||
: | |||
e | |||
4 | |||
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}} |
Latest revision as of 15:16, 19 December 2021
ML20207N166 | |
Person / Time | |
---|---|
Site: | Seabrook |
Issue date: | 12/31/1986 |
From: | Kamal Manoly, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
To: | |
Shared Package | |
ML20207N160 | List: |
References | |
RTR-REGGD-01.029, RTR-REGGD-1.029 50-443-86-51, IEB-79-14, NUDOCS 8701140025 | |
Download: ML20207N166 (28) | |
See also: IR 05000443/1986051
Text
.
..
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No. 50-443/86-51
Docket No. 50-443
License No. CPPR-135 Category A
Licensee: Public Service of New Hampshire
P.O. Box 330
Manchester, New Hampshire 03105
Facility Name: -Seabrcok Station, Unit #1
Inspection At: Seabrook, New Hampshire
Inspection Conducted: October 28-31, 1986
""
Inspectors:
'
/YTC/86
K. Manoly, Lead Reactor Enginelir date
Approved by: ,, /2/J//84
Strosnider, Chief, Materials and date
yProcessesSection,EB,DRS
,
, o
i
7:
.
Table of Contents
Page
Executive-Summary 1
1. Persons Contacted 2
2. Inspection Objective and Scope 2
3. Allegation Description (RI-86-A-0113) 3
4. Safety Related Piping Systems As-Built Inspection 4
4.1 Overview of the Piping As-Built Program 4
4.2 NRC Walkdown verification of Piping Installations 8
4.3 Findings 9
4.4- Conclusion 10
5. Review of Other Program Activities 11
5.1 General 11
5.2 IBuilding Beam Verification Program 11
5.3 Seismic II/I Interaction Program 12
5.4 Failure Modes and Effects Analysis (FMEA) Program 13
5.5 Conclusion 14
6. Exit Meeting- 14
Attachments
Appendix I
.
.
EXECUTIVE SUMMARY
Region I performed a special inspection to evaluate alleged discrepancies at
Unit I of Seabrook Station related to the as-built drawings of safety related
piping and support systems. The NRC inspection also covered several other
programmatic activities which included the Building Beam Verification, the
Seismic II/I Interaction and the High/ Moderate Energy Pipe Break Whip and Jet
Impingement Load Verification Programs.
The allegation was made by a former licensee contractor and it primarily dealt
with concerns over the accuracy of the measurements provided on the as-built
drawings and their impact on the adequacy of the piping stress reconciliation
effort and other programs that interfaced with as-built conditions. Details
of the alleged discrepancies in the as-built piping and support drawings and
the NRC evaluation of these discrepancies are provided in Appendix I of this
report.
The processes of piping installation and as-built verification had been
examined and-reviewed by the NRC throughout the construction phase. This
special NRC inspection, in response to the allegation, consisted of:
(1) re-examination of the programs which governed the piping as-built verif-
ication effort (Section 4.1) and the other activities mentioned by the alleger
as potentially deficient (Section 5), and (2) verification of final as-built
piping drawings by performing independent measurements of piping sections
addressed in the allegation and other randomly selected piping systems (Section
4.2).
The NRC review of the programs for piping as-built verification and stress
reconciliation were found to be consistent with accepted industry practice and
were in compliance with NRC requirements set forth in I.E.Bulletin 79-14 for
as-built verification of safety related piping systems. Based on NRC
independent measurements of plant systems, it was found that the final as-built
piping drawings were within acceptable tolerances set by the reconcilation
criteria. The as-built drawings supplied by the alleger were not consistent
with the plant as-built final drawings and apparently were drawings used in
earlier evolutions of as-built verifications.
The approach used by the alleger in performing the interference evaluation
relies on very precise and accurate measurements and a reference system that is
primarily used as a construction aid. It is not necessary, nor is it common
industry practice that measurements of this precision be made to support the
pipe stress reconciliation effort. The use of building reference points
introduces errors because this information is not updated and only utilized to
aid construction forces in locating supports in a general areas. It has no
bearing on final interferences or stress calculations.
Based on the NRC evaluation of licensee programs for the performance of safety
related activities, it was concluded that the programs had met the intent of
the regulations and were substantially in conformance with established industry
standards. The NRC concluded, therefore, that the allegation involving the
adequacy of safety related piping as-built drawings and other safety related
activities at the Seabrook Station is unsubstantiated. No violations were
identified during this inspection.
_
y
9
.
2
1.0 Persons Contacted
1.1 New Hampshire Yankee (NYH)
- J. DeVincentis, Director of Engineering
- T. Pucko, Senior Licensing Engineer
- T. Cizauskas, Lead Mechanical Engineer
- D. Perkins, Licensing Engineer
- S. Sadosky, Manager EAR Program
- W. Sullivan, Senior QA Engineer
1.2 United Engineers and Constructors (UE&C)
8. Huselton, Project Engineering Manager
G. Tuday, FMEA Group Engineer
D. Mehta, Seismic Coordinating Engineer
J. Parisano, Piping Engineer
1.3 CYGNA Energy Services
- P. Baughman, PAPSCOTT Coordinator
1.4 Computerized Interference Elimination (CIE)
S. Mitchell, President
S. Nicholson, General Manager
1.5 U.S. Nuclear Regulatory Commission (NRC)
- A. Cerne, Senior Resident Inspector
- D. Ruscitto, Resident Inspector
D. Haverkamp, Reactor Project Engineer
- Denotes personnel present during the exit meeting on October 31, 1986.
2. Inspection Objective and Scope
The objective of this inspection was to evaluate alleged discrepancies in
,
the as-built drawings of Safety Related (S/R) piping systems qualified by
l
Westinghouse (W) and United Engineers and Constructors (UE&C), and to
assess the potential effect of utilizing these drawings in the performance
of activities involving Building Beam Verification, Seismic II/I Interaction
and Failure Mode and Effects Analysis. To achieve this objective, the
inspection focused on the examination of programs which govern the above
activities and on the performance of independent measurements of piping
sections addressed in the allegation and other randomly selected piping
systems.
l
l
l
- _ _ _ _ _ _ _ _ _ . _
. . . . _ _ - _ . ,_. -
.
.
3
3. Allegation Description (RI-86-A-0113)
The Region I (R-I) Office of the NRC was notified by the Region III office
of an allegation involving as-built drawings of safety related piping
systems at the Seabrook station. The Region III staff was informed of the
allegation on August 5, 1986 while conducting an interview with personnel
from Computerized Interference Elimination (CIE), a former contractor to
New Hampshire Yankee (NHY), regarding alleged discrepancies in as-built
drawings of piping systems in Units 1 & 2 of. Byron Station. A copy of the
allegation interview transcript was transmitted to the R-I Office on
September 19, 1986. Two lead Reactor Engineers from the R-I Office
traveled to Redmond, Washington on October 21, 1986 to interview the two
principal allegers from CIE identified above.
The allegers identified certain concerns regarding the existence of
discrepancies in as-built drawings of safety related piping systems
designed by Westinghouse {W) and United Engineers and Constructors (UE&C)
at the Seabrook Station. CIE provided the NRC staff with copies of piping
drawings prepared by W and UE&C relating to the systems involved in the
allegation and six other drawings prepared by CIE depicting the alleged
discrepancies. The discrepancies were noted during the performance of
interference verification utilizing drawings provided by the licensee (NHY)
and information obtained by telephone from NHY, W and UE&C. Five of the
six alleged discrepancies involved walkdown, marked-up drawings by W which
were not approved as final. The allegation primarily dealt with concerns
over the accuracy of the measurements provided on the drawings and the
impact on the adequacy of the licensee's pipe stress reconciliation efforts.
-
It also referenced other design activities which could potentially be
"
affected as a result of using input data from as-built drawings containing
discrepancies. These activities included Building Beam Verifications,
Seismic II/I Interaction, and High/ Moderate Energy Pipe Break Whip and Jet
Impingement Load Verification Programs.
The alleged discrepancies in the as-built piping drawings involved apparent
offsets in the location of certain piping sections or supports. The offsets
were noted as the alleger attempted to trace. piping system configurations
and related supports from information provided on drawings of walkdown
isometerics, penetration sleeve details, building steel floor layout,
concrete wall penetration location, and pipe supports detail / reference
location. The magnitude of the maximum alleged dimensional discrepancy
was approximately I'-6".
'
The specific discrepancies, according to the alleger, are summarized in
Appendix I of this report.
.-
e
4
4. Safety Related Piping Systems As-Built Inspection
4.1 Overview of the Piping As-Built Program
The scope and controlling procedures for the as-built program of Safety
Related (S/R) piping systems differed according to the organization
responsible for the erection or the design and reconciliation of com-
pleted installations. Though the majority of S/R piping and support
installations (except for the primary coolant loop) were fabricated
by DRAVO and erected by Pullman Power (P-H), the responsibility for
the design and reconciliation of ASME Class I piping was that of W
and for Class II, III and ANSI 831 piping was UE&C. As-built verifi-
cation of completed piping installation was conducted twice, first by
P-H as part of the ASME code "NA" certification prior to turnover and
second, by W and UE&C in support of the stress reconciliation effort
of their respective piping.
The inspector conducted interviews with cognizant licensee representa-
tives and reviewed procedures (Attachment 1) established by Westinghouse
(W) and UE&C which governed some of the activities performed by the
Piping and Pipe Support Closeout Task Team (PAPSCOTT). These activities
included the as-constructed walkdowns and the stress analysis reconcil-
iation and pipe support verification tasks in support of the ASME N-5
certification program.
The flow chart in figure 4-1 depicts the sequence of activities
involved in the ASME completion program for piping systems from the
design phase through code certification. The numbers in the flow
chart blocks identify the sequence of certain activities performed by
the engineering / design and installing organizations. The as-engineered
piping was typically shown on design isometrics by W or UE&C (block
1). The desigr. isometrics were transmitted to the fabricator (DRAVO)
for preparation of piping spool drawings. These drawings were used
by the installer (P-H) for the preparation of erection drawings and
subsequent piping erection (block 2). Field verification of piping
and related components installed in accordance with ASME Section III
was performed by the installer prior to turnover to satisfy code
certification requirements. Data verified during the installer's
walkdown were either incorporated in revised erection drawings or
red-lined on current isometrics (block 3). Walkdown verification of
as-built piping installations was subsequently conducted by the
engineering / design organization for the purpose of piping stress
reconcilation. Though some of the verification attributes were
common to both walkdowns, the piping data verified during the recon-
cilation effort were pertinent to piping stress analysis and code
acceptance limits. Results of the latter walkdown were recorded on
marked up isometrics (Block 4). These isometrics were considered
final when the marked walkdown drawings were signed as approved, as
in the case of W drawings, or when stamped "As-Constructed", as in
the case of UE&C drawings.
. . . _ - - -
.g'-
%
.
'
5
- The significant features.cf the piping as-built program which related
to the allegation concerns are presented below.
I. As-Built Walkdown Prior to Turnover-
--
Interface activities between P-H, UE&C and the startup test
department, relative.to the release and turnover of systems
were described in P-H Procedure X-23.
--
Documentation of field verifications, final inspection and
final _ review of ASME III piping was governed by P-H Procedure
X-4.
---
The walkdown was conducted by P-H field engineering in. accord-
ance with walkdown_ implementing Procedure No. X-30 for field
verification and recording of piping linear measurements
and elevations.
--
Field verification of supports was conducted to P-H Procedure
JS-IX-6.
--
Walkdown packages including as-built isometric drawings and
walkdown verification forms were transmitted to P-H/QC for.
_ performance of final piping and support inspections.
~
--
Walkdown packages were transmitted to P-H/QA for review of
completeness prior to the sign off on ASME Code "NA" certi-
fication.
--
Data recorded during the as-built walkdown were either_incor-
porated in revised erection isometric drawings (prior to mid-
1984) or red-lined on current erection isometrics (after mid-
1984).
II. ' Piping Qualified by W
,
l
--
W generated the piping design isometrics using original UE&C
j isometrics, and performed the piping stress analyses of record,
f --
As-built piping walkdowns were performed by teams including
engineering and surveying personnel to' record piping config-
i uration on the design drawings in accordance with Procedure
l- SSP-1. Angular measurements were recorded at elbows and pipei
l bends, though no specific tolerance was provided in procedure
! SSP-1. A tolerance of 5 degrees in angular measurements was
- noted in a correspondence between W and NHY.
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.
.
7
--
Marked-up walkdown drawings were reviewed against change
documents and other design information for evaluation of
discrepancies identified during the walkdown process.before
final approval of the drawing.
--
Reconciliation of as-built installations addressed five
categories involving piping configuration, pipe supports,
pipe properties, loading conditions and interferences.
--
The acceptance criteria for the reconciliation effort were
stated in Procedure SSP-2.
--
Piping neasurements which exceeded the reconciliation accept-
ance criteria were reconciled either by hand calculations or
computer re-analysis, and noted on final analysis isometric
drawings. However, measurements which fell within the accept-
ance criteria were not noted on these drawings.
--
Final piping as-built packages consisted of approved walkdown
isometric drawings containing three signatures, final analysis
isometric and stress analysis report.
III. Piping Qualified by UE&C
--
UE&C generated piping isometrics which were used by
Pullman Power for the preparation of installation drawings.
--
Location of piping supports during the installation phase
was based on measurements provided on each support drawing
from nearby building elements such as walls, beams, columns,
etc. These dimensions were provided in addition to location
plan measurements which were intended for reference purpose
only.
'
--
UE&C utilized Pullman drawings and related ECA's and NCR's
, to update the piping isometrics.
--
The elements of the piping as-constructed walkdown data
collection were described in procedure FAEP-1. Design
drawings and checklists were used to record walkdown data
which include: (1) location of pipe supports relative to the
piping; (2) location of floor / wall sleeve and gaps relative
to piping; (3) pipe support function; (4) pipe support gaps;
(5) location / orientation of welded attachments; and (6) build-
ing location dimensions.
--
Additional requirement regarding the walkdown data collection
and the accuracy of measurements was provided in Technical
Procedure TP-26.
1
-_ - . .--
_ , . - . _ _ . . _ _ .- ,- ,
F
.
.
8
--
Verification of piping as-built angle data was not addressed
in the walkdown procedures. The rationale for not performing
angular measurements during this phase included consideration
of very stringent tolerances in the location of end components
and the fabrication and erection of pipe support components
and piping spools. Variations in piping segments length due
to cutting or addition of sections during fit-up of spool
pieces were verified and reconciled during the walkdown effort.
Results of a confirmatory walkdown conducted in 1983-1984 were
provided in support of the above rationale. The walkdown
involved approximately 500 drawings for verification of piping
bend angles as well as end-components and support locations.
Evaluation of the results from 130 drawings indicated that
angles were within 5 tolerance of drawings or ECA's.
--
Dimensions verified in the walkdown effort were circled on
the final as-constructed drawings.
--
The evaluation criteria and acceptable tolerances used for
the reconciliation of as-constructed installation were stated
in Appendix "C" of Procedure PGL-7. The tolerances were
consistent with the recommendation in a technical position
paper on piping installation tolerances sponsored by the
PVRC technical committee on piping systems and published in
Bulletin 316 of the Welding Research Council.
--
Firal as-built packages consisted of isometric "As-Con-
structed" drawings reflecting walkdown measurements, final
analysis isometrics and stress analysis reports.
4.2 NRC Walkdown Verification of Piping Installations
A physical inspection was conducted, by the NRC inspector of piping
installations referenced in the allegation and other randomly selected
systems. The inspection included several piping segments of the RHR
system inside and outside the containment (by W and UE&C) in addition
to segments of the piping system from the accumulators (No.1 & 2).
The inspection utilized W stress isometric and UE&C as-constructed
drawings. Piping segments and drawings used in this effort are
identified in Attachment 2 to this report.
The purpose of this effort was to examine the conformance between
installed piping systems and the information recorded on walkdown and
analysis isometric drawings. Though the processes of piping installa-
tion and as-built verification were examined and reviewed by the NRC
throughout the construction phase until completion, this effort was
undertaken primarily to assess the specific discrepancies identified
in the allegation and to further examine piping installations in
general, for potential non-conformances of a type which would invalidate
the piping stress reconciliation effort. Examples of previous NRC
inspections of piping as-built verification inspections can be found
in Inspection Report Nos. 50-443/85-09, 85-15, 86-14, 86-43 and 86-46.
.
.
9
The verification walkdown included visual inspection and performance
of independent measurement of selected piping installations. The
attributes of the inspection included the following:
--
Checking actual configurations against piping drawings.
--
Performing linear measurements between components and supports
along the piping using a tape measure.
--
Checking piping angles either visually or by trigonometric
correlation of linear measurements on piping legs where possible.
--
Checking valve types and tagging.
--
Checking support types to verify restraint function.
--
Checking clearances between piping and supports where required.
A total of 153 linear measurements were verified during the piping
walkdown, of which 98 were performed on W piping and 55 on UE&C
piping. It should be noted that the majority of piping inspected
was insulated; thus, measurements which were difficult to perform
were considered acceptable if within 2" of recorded dimensions.
Measurements performed on W piping which exceeded the walkdown
acceptance tolerance were later compared against recorded measure-
ments on walkdown isometric drawings.
4.3 Findings
The following findings are based on the NRC review of the piping
as-built program, walkdown verification of selected piping installa-
tions, and examination of alleged discrepancies.
1. The procedures established for the performance of piping as-built
walkdown verification and stress reconciliation efforts were
found to be consistent with accepted industry practice. Further-
more, the licensee's approach to the as-built process met the
requirements and intent of the NRC's I.E.Bulletin 79-14 in that
it provided the needed verification of the attributes and dimen-
sions, within acceptable tolerances, which define the relative
'
configuration of piping and are considered critical to design
and the validity of the piping stress analysis. Verification of
reference dimensions which affect the global position, relative
to the building structure, of piping and supports in three
dimensional space was not generally included in the as-built
program and is not required to be included. Verification of
dimensions between piping systems and building structures is not
required for stress reconcilation since the piping stresses are
determined by the piping system geometry not the piping to
building structure dimensions.
. - _ . _ . _ . _ __ _ __
.
.
10
2. The alleged discrepandes in as-built drawings of safety related
piping systems were for the most part incorrect due to:
a) use of W walkdown drawings which were not final,
b) introduction of erroneous values of piping dimensions at
flued head sleeve anchors in the attempt to correlate dimen-
sional information from sleeve detail drawings by UE&C and
walkdown drawings by W (apparently the result of miscommuni-
cation between the alleger and field personnel),
c) use by the alleger of several values beyond their intended
accuracy, particularly with regard to support location
reference dimensions and location of both building steel
members and wall penetrations, and
d) reliance by the alleger on exact values to be recorded on
piping walkdown drawings while ignoring linear and angular
tolerances which were inherent in the field walkdown process.
Detailed evaluation of the specific alleged discrepancies is
provided in Appendix I of this report.
3. Minor dimensional discrepancies were noted between linear measure-
ments performed during the NRC piping walkdown and dimensions
recorded on the walkdown drawings. A total of eleven (11) discre-
pancies was found, of which eight (8) were within 3" of the walk-
down drawings and the remaining three within 3.75", 5.5" and 6"
respectively. It should be noted, however, that three of the
dimensions with discrepancies involved measurements which were
difficult to perform due to insulation and inaccessability of the
piping system. Furthermore, in all of the dimensions involving
discrepancies, the difference between the design and measured
dimensions were well within the acceptable tolerance set by the
reconciliation criteria. Thus, a re-analysis of associated piping
would not have been required.
4.4 Conclusion
The inspector concluded that the program for the as-built and reconcil-
iation process of safety related piping and support systems, qualified
by W and UE&C at the Seabrook Station, were consistent with accepted
industry practice and no items of non-compliance were identified with
regard to NRC requirements set forth in I.E.Bulletin 79-14. Further,
upon review of the alleged discrepancies and performance of walkdown
verification of completed piping installations, it was apparent that
the as-built drawings had reasonably depicted the piping configurations
as required for performing the stress reconciliation effort. It was
also concluded that the approach utilized by the alleger in performing
the interference verification relies on very precise and accurate
.
.
11
measurements of piping components and building elements. Some of these
measurements are recorded with tolerances (as in the case of piping and
support systems), and the remaining are not typically verified in the
as-built walkdown (as in the case of support reference dimensions,
penetration and building steel locations, etc.). It is not necessary,
nor is it common industry practice, that these precise measurements be
made to support the pipe stress reconciliation effort.
Based on the above, it is concluded that the allegation involving the
adequacy of as-built safety related piping systems at the Seabrook
Station is unsubstantiated.
5.0 Review of Other Programmatic Activities
5.1 Gereral
The NRC review included an assessment of several other programmatic
activities performed by the licensee which were addressed by the
alleger as potentially deficient due to the alleged dimensional
discrepancies. The programs covered in this effort included the Beam
Verification, the Seismic II/I Interaction, and the Failure Mode and
Effects Analysis Programs. The review focused primarily on the scope
and implementation of these programs to verify their conformance to
acceptable industry standards and their compliance to NRC regulations.
The review also covered the interface between these activities and
the piping as-built verification effort to assess the alleged potential
for ineffective evaluations as a result of using the piping as-built
drawings in the performance of these programs.
5.2 Building Beam Verification Program
The purpose of this effort was to verify that the design of category
I structural steel, which was based on assumed loads, was adequate
for final as built system loads. The program was managed by UE&C,
and described in technical procedure TP-16. It was initiated in 1983
with the establishment of a data base of all appropriate loads required
for the beam verification effort. The original design was based on
consideration of assumed uniform loads in addition to known heavy
attachment and equipment loads. During this design phase, the intent
was to maintain flexural beam stresses below 18 ksi.
The beam verification program was carried out in two phases. The
scope of the first phase included an initial verification of framing
systems using discrete design loads and locations for major attach-
ments, such as large bore pipe supports and equipment, and appropriate
(envelope) uniform loads for attachment of cable tray, conduit, I&C,
and small bon pipes. Structural weights and live operational loads
were also considered in this phase. The magnitudes of selected
envelope uniform loads in different plant zones were based on walk-
downs performed in 1984.
.
.
12
Beams evaluated in the first phase whose flexural stresses fell
between 18 and 22 ksi were designated as heavily loaded beams. Those
which exceeded 22 ksi were designated as critically loaded beams and
painted with an orange paint. The painting was intended to prevent
any attachments to these beams without prior approval from the
structural group. Re-evaluation of critically loaded beams was
performed using more refined analytical techniques and actual attach-
ment loads in lieu of assumed conservative uniform loads.
The second phase in the verification program involved the incorporation
of PAPSCOTT reconciled piping support attachment loads. The following
three categories of beams were considered in this re-evaluation:
--
Typical beams (stressed below 18 ksi) were re-analyzed if the
magnitude of uniform loads had increased significantly or if
attachments of piping 4" in diameter or larger were added.
--
Heavily loaded beams were re-evaluated for any additional loads
to ensure that flexural stresses were below 22 ksi.
--
Critically loaded beams were re-evaluated if the applied loads
from the first phase had increased. A walkdown was typically
performed to verify the as-built geometry, loading and boundary
conditions for these beams.
-This second phase of the beam verification program was completed in
July of 1986.
5.3 Seismic II/I Interaction Program
The program, described in Technical Procedure TP-4 (Review of Non-Safety
Related Equipment, Systems, and Supports located in Safety Related
Buildings) was conducted by UE&C to meet the requirements of Regulatory
Guide 1.29, Position C2. The Regulatory Positions was implemented by
,
either of the *-llowing approaches:
1
(a) Providing seismic supports to non-safety related systems and sup-
ports (such as piping, ducts, cable trays, conduits, bus ducts,
and I & C trays and tubing) located in safety related baildings
to prevent their failure and damaging of safety related systems
and components during a seismic event.
(b) For items which were not seismically supported, Failure Modes
and Effects Analysis (FMEA) was performed to assure that they
were isolated by their location and their postulated failure
would not impact on safety related components during a seismic
event.
'
.
._- . _ - . . - .
.
.
13
-The procedure (TP-4) provided a tabulation of non-safety related items
which were installed in safety related buildings. These items (generally
considered large equipment) included tanks, instrument racks, seismic
chtlier pumps, cabinets, unit heaters, radiation monitors, etc. This
equipment was listed by the building in which it was located and was
identified by its classification, tag number, type of anchorage and
relative location to other safety related equipment. Support for non-
safety related and seismically mounted equipment identified in TP-4 was
provided in special detailed drawings by the manufacturer or UE&C.
D.her small non-safety related items such as instruments, wall mounted
electrical boxes, switches, etc. were not addressed in procedure TP-4.
These were seismically mounted in accordance with typical notes and
details for I&C and conduit support drawings.
A two phase confirmatory field walkdown was instituted in early 1986 for
al) non-isolated, seismically anchored and all isolated, non-seismically
anchored equipment listed in TP-4. The walkdown was completed in the
Diesel Generator, Fuel Storage, Service Water Pump House and Service
Water Cooling Tower. This effort was discontinued, however in other
safety related areas due to lack of findings.
Licensee evaluation of the seismic II/I interaction was substantially
complete except for a walkdown which is currently being performed of all
hose reels and fire extinguishers in safety related areas for isolation
and requirement for seismic mounting.
5.4 Failure Modes and Effects Analysis (FMEA) Program
This FMEA program was initiated by the licensee to address the require-
ments of 10 CFR 50, Appendix A, General Design Criteria 4 which requires
that structures, systems, and components important to safety be designed
to accommodate the effects of postulated accidents, including appropriate
protection against the dynamic and environmental effects of postulated
pipe ruptures. The program provided evaluation of pipe whip, jet
impingement, and flooding effects on safety-related plant systems,
structures and components. The evaluation was documented in eighty-three
(83) zone reports which contained the information required to evaluate
the consequences of piping failures within the zone on essential plant
systems and components.
The program was managed by UE&C and was performed in accordance with
Technical Procedure TP-3. The procedure adopted the guidance for
postulated rupture locations, types and sizes presented in the Standard
Review Plan (NUREG-800), Sections 3.6.1 and 3.6.2. The criteria estab-
lished the specific rupture conditions to be evaluated including the
consequential effects of the ruptures.
i
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,
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.
14
The evaluation effort was accomplished in two phases. The first phase
(1982-1985) was performed using plant design drawings, such as struc-
tural, general arrangement, piping, HVAC, etc., for detection of targets
to be evaluated. The second phase consisted of plant walkdowns to verify
actual as-built conditions of safety-related systems and components
evaluated in the first phase, and to identify other safety related
systems, components and field run commodities which were not previously
addressed. The inspector was informed that the Seabrook scale model
was not utilized in the conduction of either phase. Prior to performing
the plant walkdown, an evaluation was performed of as-constructed piping
drawings by W and UE&C.to identify systems which had changed in configur-
ation to assess the likelihood of revised postulated break locations and
potential targets. Criteria for acceptability of interaction involved
considerations of system operability and/or structural functionality.
The second phase of the FMEA activities was completed in April, 1986.
5.5 Conclusion
Based on the NRC evaluation of licensee programs for the performance
of safety related activities addressed above, it was concluded that the
programs had met the intent of the regulations and were substantially
in conformance with established industry standards. Further, upon
review of the interfaces between the piping as-built program and the
Beam Verification and Failure Mode and Effects Analysis programs, it
was concluded that they were adequate for performing these activities.
Based on the above, it is concluded that the allegation involving
the adequacy of these safety related activities at the Seabrook
Station is unsubstantiated.
6. Exit Meeting
The inspector met with licensee representatives (denoted in paragraph 1)
at-the conclusion of the inspection on October 31, 1986. The inspector
summarized the purpose and the scope of the inspection arid the^ findings.
At no time during this inspection was written material provided by the
inspector to the licensee.
.
.
ATTACHMENT 1
DOCUMENTS REVIEWED
The following documents were reviewed, in part, during the course of
inspection:
Procedure No. X-30 for field verification of piping by Pullman Power
- Procedure No. X-4 for field inspection by Pullman Power
- Procedure No. X-23 for Turnover by Pullman Power
Procedure No. PGL-7 for AMSE and NNS-IA Piping and Pipe Support
Reconciliation Program by UE&C
- Position Paper on Acceptance Criteria for Piping Installation by UE&C
Technical Procedure No. TP-26 for As-Constructued Requirements of Piping
Systems by UE&C
Procedure No. FAEP-1 for ASME Field Data Completion Program by UE&C
Technical Procedure No. TP-33 for "As-Constructed" Verification Program
for ASME Piping System Installed by UE&C
- Procedure No. SSP-1 for As-Built Reconciliation Walkdown Guidelines by W
Procedure No. SSP-2 for Review of the As-Built Condition of Westinghouse
Analyzed Auxiliary Lines
Quality Control Procedure No. QCP-17-5 for N-5 Data Report by UE&C
Specification No. 9763-006-248-51 for Assembly and Erection of Piping and
Mechanical Equipment by UE&C
Procedure No. JS-1X-6 for Installation and Inspection of ASME III Pipe
Supports by Pullman Power
Procedure No. TP-3 for Conducting Failure Modes and Effects Analysis
(FMEA) Piping Failure by UE&C
Procedure No. TP-4 for Review of Non-Safety Related Equipment, Systems
and Supports located in Safety Related Buildings by UE&C
Technical Procedure No. TP-16 for Beam Verification Program
l
l
-. .
.-- - _ . _ _ _ _ - _ _
.
.
ATTACHMENT 2
Piping Qualified No. of Description of Piping
Line No. By Measure- Section Verified
Drawing No. ments
RHR1-W0013 (Sh.1) RC-13-13-601-12" W 10 Between penetration and
sleeve No. 13 A
RHR1-W0013 (Sh.2) 180-1-2501-8" W 11 Between line 160 and
penetration No. 34
RH4-W-0058(Sh.1) 58-13-601-12" W 12 Between penetration X-10
and 10-lh" horizontal
run beyond hanger No.
58-SG-07
RH4-W-0058(Sh.2) RH-160-3-2501-12" W 17 Between penetration X-13
& 160-4-2501-8" and 1-5" horizontal run
beyond hanger No.
160-SG-05
ACC1-W0155 (Sh.1) SI-201-1-601-10" W 26 Between ACC. Tank.9A
and 2'-10 " horizontal
run beyond hanger No.
201-RM-15
ACC2-W0162 (Sh.1) SI-201-1-601-10" W
-
22 Between ACC. Tank 9B :
and I'-9" horizontal
run beyond hanger No.
202-RM-09
F-800160-542.01 160-1-601-8" U&EC 35 Between penetration
X-13 and 7'-0"
horizontal run beyond
sleeve No. 1558
D-800014-491.70 RC-14-1-601-3" U&EC 20 Between line No.
l RC-13-2-601-12" and
'
10 " horizontal run
before hanger No.
'
14-SG-8
l
l
.. . . - _ _ - . . .. . ___. _ _ , .
_ _ ._
.
.
Appendix I
Details of the alleged discrepancies in as-built piping drawings are given below.
For each of the six descrepancies, the description, according to the alleger's
drawings, is followed by the results of the NRC evaluation. Simplified
figures, projected from the allegers drawings, are included to illustrate the
configuration and geometry of piping, supports and building sections involved.
a. Descrepancy Drawing No. 53-A
Details: W piping No. RC-13-13-601-12" shown on sheet 1 of Dwg. No.
RHR1-W0013: The piping runs from penetration No. X-9 to sleeve No. 13A
(incorrectly referenced as sleeve No. 33). The piping was shown by the
allegers analysis to be interfering with the concrete wall as it penetrates
sleeve No. 13A. An offset of approximately 4" was shown between the piping
and sleeve centerlines. (See attached Dwg. No. 1)
NRC Evaluation: The l'-0" dimension between the inside face of the con-
tainment at penetration No. X-9 and the weld line is irrelevant. The 12'-8
3/4" starting dimension shown on the run of piping (No. RC-13-13-601-12")
from the weld line to the bend is incorrect. The measurement should be from
the penetration guide at the face of the lug. The incorrect assumption
introduced-an additional 6 3/4" to the piping run length towards the east
direction. Further, the opening for sleeve No. 13A was shown to be approxi-
mately 16" in diameter, whereas it measured approximately 23". Correction
of both errors in the alleger's analysis would eliminate the discrepancy ana
allow the pipe to pass through the sleeve with no interference.
b. Discrepancy Drawing No. 53-B
Details: UE&C piping No. RC-14-2-A7-4" and support No. 14-SG-7 shown on
Dwg. No. D-800014-491-70: The piping branches off W piping header No.
RC-13-13-601-12" identified in (a) above. The piping at the location of
the support was shown to be offset by approximately 9". (See attached-
Dwg No. 2)
!
NRC Evaluation: Three dimensional errors were noted. The first involved
~
the incorrect point of line No. RC-13-13-601-12" from penetration No. X-9,
identified in "a" above, which resulted in the introduction of a 6 3/4" error.
The second and third involved two dimensions on east-west runs of piping
No. RC-14-2-A7-4" by UE&C. The dimensions which were shown on Dwg. No. 538
as 2-6 1/2" and 2-11" were recorded on UE&C "as constructed" drawing No.
- D-800014-491.70 and verified by the NRC walkdown as 2'-6" and 2'-91/4".
These two errors introduced an additional 2 1/4" in the east direction.
l The three errors collectively resulted in the alleged offset of 9" between
the piping and the support.
,
j
l
. -
. . _ , -_
_-
.
.
Appendix I 2
c. Discrepancy Drawing No. 53-C
Detail: Two related discrepancies in: (1) W piping No. RH-160-3-2501-12"
shown on sheet 2 of Dwg. No. RHR4-W0058; (27 W piping No. RH-180-1-2501-8"
shown on sheet 2 of Dwg. No. RHR-1-W0013; (3) UE&C piping No. RH-182-1-2501-3/4"
shown on Dwg. No. 800182-S43.00; and (4) UE&C piping No. RH-181-1-2501-3/4"
shown on Dwg. No. 800181-543.01. The four piping lines e.re connected in a
closed loop in the same sequence listed above where line No. 181 connects
back to the main header No. 160. The first discrepancy involved an offset
in the connection between lines No. 181 & 160 of approximately 10". The
second discrepancy involved an offset in the location of support No. 180-SG-4
on line No. 180 from its designated location on the building steel. (See
attached Dwg No. 3)
NRC Evaluation: The dimension 6'-8 9/16" between-the elbow on line No.
RH-180-1-2501-8" and the junction to branch line No. RH-182-1-2501-3/4" is
incorrect. The dimension was shown on W stress isometric as 7'-7 7/8" and
-
was measured during the NRC walkdown as 7'-81/4". The alleged offset
discrepancy of 10" could be substantially eleminated if the difference
between the correct and the alleged dimensions is multiplied by the cosine
of the angle between the line and the east-west axis (20 ). The alleged
offset in the location of support No. 180-SG-4 on line no. 180 could be
substantially reduced if the 24'-3 7/8" dimension on line no. RH-160-3-2501-12"
is corrected to 25'-10", and the starting point of the same line from the
lug at penetration no. X-13 to the elbow is corrected to 2'-91/2". This
is addressed further in the next alleged discrepancy. Further, it is
significant that the second alleged discrepancy was based on correlation
of piping as-built verification measurements with dimensions obtained from
the pipe support reference location and the building steel layout drawings.
Since neither the support reference nor the building steel location
dimension was verified (or required to be verified), the alleged discrepancy
is deemed erroneous.
d. Discrepancy Drawing No. 53D
Details: W piping No. RH-160-3-2501-12" shown on sheet 2 of Dwg. No.
RHR4-W0058. Two discrepancies were noted: The first involved an offset
in the location of supports No. 160-SG-5 and 160-RM-6 on the above line
from their designated location on the location plan of the respective
support drawings. The offset was approximately 18" on both supports. The
second discrepancy involved an offset in the connection of line No.
250-4-2501-2" to line No. 160-5-2501-8". The offset was shown as 11 13/16"
in the east-west direction and l'-3 7/8" in the north-south direction.
(See attached Dwg No. 4)
-_. _ _ - - - - - . _ _ - - - -
.
a
Appendix I 3
NRC Evaluation: The alleged offsets in both support locations and the branch
line connection were caused by two dimensional discrepancies on the piping
run in addition to the use of reference centerline dimensions from structural
drawings in locating pipe support attachments. The starting 2'-9 1/2" dimen-
sion of piping No. RH-160-3-2501-12" from penetration No. X-13 to the first
elbow should be measured from the face of the lug rather than from the piping-
to-sleeve weld line as shown on Dwg. No. 53-D. The other dimensional discrep-
ancy involved the length of the piping run from the elbow (near penetration
X-13) to the first piping bend. The dimension was noted as 24'-3 7/8" on Dwg.
No. 53-D and on the W preliminary walkdown drawing. The correct dimension
was shown on the final W isometric drawing as 25'-10". Since the dimensional
error in the W drawing involved a walkdown drawing which was still in process,
the inspector could not determine with certainty whether the internal checks
by W had independently identified the error. Nevertheless, the alleged off-
sets can be substantially eliminated when the above dimensional corrections
are incorporated.
e. Discrepancy Drawing No. 53-E
Details: UE&C piping No. 160-1-601-8" shown on Dwg. No. F-800160-542.01.
The piping is routed through six penetrations. The discrepancy involved an
offset between the piping and penetration No. 1416 by approximately 3.5"
towards the north direction. It also involved an offset between the same
piping and penetration No. 1584 by approximately 3.5" towards the south'
direction. (See attached Dwg No. 5)
NRC Evaluation: The alleged discrepancy was determined to be erroneous
because it was based on inherently incorrect assumptions and misunderstand-
ings of the as-built process. The relative locations and orientations of
the six penetrations involved in this discrepancy were neither verified
with respect to each other nor with respect to a fixed reference point,
and are not required to be, during the as-built process. In addition,
penetration centerlines were not necessarily parallel to, or concentric
with, centerlines of piping which passe through these penetrations. Any
possible angularity, within the 5 tolerance, between the centerline of
the piping run (No. 160-1-601-8") and the penetrations involved will
eliminate this apparent discrepancy. % NRC inspector's walkdown of the
piping involved between penetrations Ro. !-13 and 1558 confirmed the
adequacy of measurements on the dv >nr * ucted" drawing by UE&C within
specified tolerances.
f. Discrepancy Drawing No. 53-F
Details: Configuration of W piping No. RC-13-13-601-12" from penetration
No. X-9 or sheet 1 of Dwg. No. RHR-1-W0013 (incorrectly identified as piping
No. RC-13-1-2501-12"): The piping configuration was shown twice using dimen-
sions from W drawing above, and Pullman Power erection Dwg. No. RC-13-06.
The two configurations were offset by approximately 5'-0" in the east-west
direction primarily due to the difference in length of the piping run from
the penetration. The other discrepancy in the same drawing depicted the
distance between the two legs of a U-bend as 2'-9" according to W drawing
and as 3'-6" according to Pullman drawing.
.
I
'
, .
Appendix I 4
NRC Evaluation: The dimension of piping No. RC-13-13-601-12" from penetra-
tion No. X-9 to the first bend was consistent between W and Pullman erection
drawings, contrary to the 5-0" offset shown on Dwg. 53-F between the two
layouts. Further, the apparent discrepancy in the piping dimension, between
the two legs of the U-bend, was resolved since it was noted and verified as
3-6" on both W final isometric and Pullman erection drawings.
e
4
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