ML19220C368
| ML19220C368 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/13/1976 |
| From: | Barker F, Heishman R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220C364 | List: |
| References | |
| 50-320-75-14, NUDOCS 7904300482 | |
| Download: ML19220C368 (25) | |
See also: IR 05000320/1975014
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I:I Forcr 12
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'Jan 75) (F.cv)
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U. S. NUCLEAR RECUL* STORY C0:C!IES10::
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0FFICE OF II SPECTIO'l AND F.NFORCCIE'TT
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RECION I
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E Inspection Report No:
50-320/75-14
_ Docket No:
50-320
Licensec: }ktropolitan Edison Company
Licence Uo:
CPPR-66
B x 542
Priority:
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Reading, Pennsylvania 19603
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Ca tegory:
Safcquards
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Middletown, Pennsylvania (TMI-2)
Gr up-
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Location:
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Type of Licensec:
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Routine - Unannounced
73
of Insp ction:
December 15-18, 1975
Dates of Inn; ection:
Oct ber 20-23, 1975
Dates cf Previcus In pection:
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Reportin;, Inspecter: _
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[.NarrowjReactorfsp ' or
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Accompanying Inspectors: M
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F. Barker, Reactor Inspector
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QL l b,I$]fD
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DATi:
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A. Finkel, Reactor Inspector
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DATE
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Other /.ccompanyinp, Personnel:
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Reviewed By:
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[R. F He shnan, . crio ' Lea der
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SUNIARY OF FINDINGS
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Enforcement Action
A.
Items of Nonecmo11ance
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Deficiency
Contrary to 10 CFR 50, Appendix B, Criterion VII:
Documentary evidence of conformance to procurc=ent requirements
was inco=plete for Spool Piece 2-DH-124 and for Haagers BSH 88 and
89.
(Details, Paragraph 2)
B.
Deviations
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None
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Licensee Action on Previousiv Identified Enforcecent Items
The deviation with respect to chloride and nitrate content of grout has
been resolved.
(Detaile,, Paragraph 3)
Design Changes
None
Unusual Occurrences
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None
Other Significant Findings
A.
Current Findings
1.
The following items are unresolved:
Installation of cable tray and cor.duit hangers in accord-
a.
ance with sketches which have not been approved by
engineering. (Details, Paragraph 5)
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b.
Lack of procedures to require temperature conditioning
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of cable prior to cable pulling as recommended by the
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manufacturer.
(Details, Paragraph 6)
Angular misalignment at joint 128Q between spool piece
c.
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DH 128 and penetration No. 52 and failure to provide
tolerance limits for such misalignment.
(Details,
Paragraph 7)
d.
Procedures are not available for control and calibration
of crimping tools.
(Details, Paragraph 4)
2.
The following items are considered to be acceptable:
QC procedures for electrical cables and terminations.
a.
(Details, Paragraph 8)
b.
Training and qualification of QA/QC personnel.
(Details,
Paragraph 9)
Observation of cable pulling.
(Details, Paragraph 10)
c.
d.
Conformance of installed piping to drawing and location
requirements.
(Details, Paragraph 11)
Observation of welding in progress, completed welds and
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veld records ; Decay Heat and NuclearService Water lines.
(Details, Paragraph 12)
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B.
Status of Previousiv Reported Unresolved Items
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The following items have been resolved:
1.
Audit of vendor documentation.
(Details, Paragraph 13)
2.
Seismic integrity of supports for Control Rod Drive AC
Breaker Cabinets.
(Details, Paragraph 14)
3.
Modification of reactor internals handling fixture.
(Details,
Paragraph 15)
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Procedure for Qualified Release of nonconforming items.
4.
(Details, Paragraph 16)
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5.
NDE Personnel Qualifications.
(Details, Paragraph 17)
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6.
UT indications on CRD motor tubes.
(Details, Paragraph 18)
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Metal coatings within reactor building.
(Details, Paragraph
7.
19)
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(Details,
Voids in exterior wall of Fuel Handling building.
8.
Paragraph 20)
Exit Interview
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18, 1975.
An exit interview was held at the site on December
Persons Present
General Public Utilities Service Corporation
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R. F. Fenti. QA Auditor
W. T. Gunn, Project Site Manager
R. W. Heward, Project Manager
P. A. Levine, QA Auditor
G. Roshy, QA Engineer
M. J. Stromberg, Sr. Site. Auditor
R. L. Wayne, QA Manager
J. E. Wright, Site QA Manager
United Engineers and Constructors
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G. M. Ahearn, Asst. Project Superintendent
J. Carrabba, Field Supervisor QC
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V. E. Cichocki, Construction /QC Coordinator Superintendent
D. C. Lambert, Field Supervisor QC
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K. Merryman, Safety Engineer
Burns & Roe
W. P. Dornsife, Asst. Project Engineer
F. X. Pindar, Jr.,' Lead QA Engineer
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The items discussed are summarized below.
In each case, the licensee
acknowledged the information.
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A.
Scope of Ir.spection
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the inspection was conducted to review
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The inspecto'r stated that
installation and QC records of safety-related piping; electrical
and the status of outstanding items.
QC procedures and installation;
B.
Enforcement Items
lack of complete documentation for spool
The inspector stated that
piece 2-DH-124 and pipe hangers BSH 88 and 89. is considered to be an ite=
of noncompliance. (Details, Paragraph 2)
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C.
Unresolved Items
The inspector identified the items listed in Part A-1 of Other Sig-
nificant Findings of the Se= mary of Findings and stated that these
items are unresolved.
(Details, Paragraphs 4, 5, 6 and 7)
D.
Acceptable Items
The inspector identified the items listed in Part A-2 of Other
Significant Findings of the Surnary of Findings and stated that
these ite=s are considered to be acceptable. (Details, Paragraphs
8, 9, 10, 11 and 12)
E.
Previousiv Resorted Items
The inspector identified the itc=s listed under Previously
Identified Enforcement Items and Previously Reported Unresolved
Ite=s of the Su==ary of Findings and stated that these items
have been resolved.
(Details, Paragraphs 3, 13, 14, 15, 16,
17, 18, 19 and 20)
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DETAILS
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1.
Persons Conracted
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General Public Utilities Service Cornoration
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R. F. Fenti, Quality Assurance Auditor
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W. T. Gunn, Site Manager
N. Hollerbush, QA Engineer
P. A. Levine, QA Auditor
D. Perry, QA Engineer
G. L. Roshy, Quality Assarance Engineer
M. J. Stomberg, Site Quality Assurance Auditor
J. E. Wright, Quality Assurance Manager
J. H. Wright, Resident Civil Engineer
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United Engineers and Constructors
S. Abbott, Welding Superintendent
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V. E. Cichocki, Construction /QC Superintendent
R. Crofton, Welding Engineer
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B. Glick, Uelder
C. W. Hunter, Electrical Supervisor
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M. Mason, QC Engineer
J . . C. Spinak, Lead QA Engir.eer
Babcock and Wilcox
B. E. Treadway, Project Mancger
R. Kunz, QC Supervisor
D. Larson, Project Engineer
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Conam inapection, Inc.
P. Rentzell, Site Supervisor
K. Hobba, Welding Records Coordinator
J. McKevis, Inspector
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2.
QC Documentation
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The inspector cy.amined the documentation listeo below for selected
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pipe hangers and spool pieces.
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a.
Spool Piece No. 2-CF-7 (Core Flood System)
(1) Receiving Inspection Report No. 92 dated January 6, 1973
which had been signed by Receiving Inspection and the
Authorized Code Inspector.
(2)
M. W. Kellogg (} EGO Company Drawing No. F-1673 for this
14-inch, schedule 160 pipe; A375 Type 304 stainless
part;
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steel; Heat No. 2193-3.
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(3) Material Test Certification from Curtiss-Wright Corporation
providing chemical analysis and physical characteristics
and certifying that this part had been hydrostatically
tested, heat treated and UT examined with no reportable
indications.
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(4) Manufacturers Data Report, Form NP-1 which cc tified
that the design, materials fabrication and inspection
comply with the appropriate chapters of USAS B31.7 and
which was signed by the Authorized Code Inspector.
Docu=entation fdr this item confirmed compliance with the
2555-64.
requirements of the FSAR and B&R specification No.
b.
Spool Piece No. 2-CF-6
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(1) Receiving Inspection Report No. 150, dated February 19,
1973 signed by UE&C Receiving Inspection and the Author-
ized Code Inspector.
(2) MWK Drawing No. F-1672 Rev. 2 wh'ich showed this part to
have been fabricated of the following pieces:
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(a) 14-inch Seamless Pipe; A-376 Type 304; Heat No.
2193-1.
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(b) 14-inch elbow;
A-403 type 304; Heat No. 120855.
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(c)
lb-inch 6000 pound half compling; A-182 Type 304;
Heat No. CF-6.
(d) 6-inch Seamless Pipe; A-312 Type 304; Heat No.
8650361.
(3) Material Test Certifications for each of the above heats
providing chemical analysis, physical characteristics
and other test results.
ReportofRTandPTinspectionresultsforvekdjoints.
(4)
(5) Weld History Records.
(6) Material certifications for consumable insert, and weld
rod.
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(7) Manufacturers Data Report - Form NP-1 which had been
signed by the Authorized Code Inspector.
This documentation confirmed compliance with t e requirements
of the FSAR and B&R Specification No. 2555-64.
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Spool Piece 2-DH-125 (Decay Heat)
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(1) Receiving Inspection Report No. 171 dated July 19, 1973
signed by Receiving Inspection and the Authorized Code
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Inspector.
(2) FEnt Drawing No. F-510 which identified the following
pieces:
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12-inch Scamics: Pipe; A-376 Type 304; Heat No.
2200-1.
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12-inch Weld ells; A-403 Type WP 304; Heat No.
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150261.
(c)
12-inch x 12-inch x 8-inch reducing tee; SA 403
type WP 304; Heat No. 150566.
06675.
(d). 3-inch pipe; A-376 Type 304; Heat No.
(3) Material Test Certifications for each of the above heats
providir,g chemical analysis, physical characteristics
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and other test results.
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(4) Weld history records and caterial certifications for con-
sumable inserts and weld rods.
(5) Reports of RT and PT inspection results.
(6) Manufacturers Data Report - Form NP-1 which had been
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signed by the Authorized Code Inspector.
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This documentation confirms compliance with the requirements
of the FSAR and B&R Specification No. 2555-64.
d.
Surge Line Assemblies A-80 and A-83
(1)
Assembly Drawings A-80 and A-83 which identified the parts
for each of these 10-inch spool pieces including specifica-
tion and type of caterial and heat numbers for each.
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(2) Material Test Certifications for each heat providing
chemical analysis, physical characteristics and other
tert results.
(3) Weld history records and material certifications for
consumable Inserts and weld rod.
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Manufacturcrs Data Report - Form NP-1 which certified.that
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the design, materials, fcbrication and inspection comply
with the appropriate chapters of USAS B31.7 and which was
signed by the Authorized Inspecter.
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Documentation for these items confirn compliance with the
FSAR requirements.
Spool Piece 2-DH-124_
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Receiving Inspection Report No. 135 dated February 14,
(1)
1973 signed by Receiving Inspection and the Authorized
Code Inspector.
(2) ' MWK Drawing No. F-509 identifying the following parts
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and requirements.
(a) 12-inch Seamless Pipe; A-376 Type 304; Heat No.
2200-3.
(b)
1\\-inch x 3/4-inch x 3-inch Lor g Lugs; Type 304
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stainless steel; Heat No. 610621.
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The drawing showed the pipe to be bent and established
(c)
requirements for heat treatment after bending,
maximun ovality and vidigage wall thickness measurements.
(3) Material Test Certifications for the above items.
Weld history records and material certifications for weld
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(4)
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rod.
(5) Report of PT inspection of welds.
2ers Data Report - Form NP-1 signed by the
(6) Manufat
Authorized Code Inspector.
MWK Drawing No. 2551 Rev.1 which had been issued for
(7)
reeleaning of this spool piece and also provided UT
measurements of the outer periphery of the bend.
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The inspector observed that records of post-bending heat
included
treatment, ovality and vidigage measurements were not
with the documentation package.
Prior to completion of the
inspection, the inspector was furnished a copy of Drawing No.
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F-509 which showed ovality measurements and stated that an
treatment chart was available at the 115; plant
approved heat
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and F-523 showing vidigase measurements and stating that
measurements would be forwarded to B&R for review.
f.
_ Hangers. Nos. BSH 88 and BSH 89 (Building Snray System)
79380 which had
(1) Receiving Checklist / Inspection Report No.
been signed by Receiving Inspection.
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Certifications which provided chemical and
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Material Test
(2)
physical data for the material in the 3/8-inch thick x 5-
inch x 14-inch lugs which had been attached by FGS; to the
assembled hangers furnished by Bergen - Patterson.
A Certification of Compliance from NWK dated March 6, 1975
(3)'
which states that the pipe assemblies listed on Packing
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List No. 165-W conforms to the requirements of B&W Spec-
ification No. 2555-64.
On the same letter, a Release for Shipment Statement had
been supplied by UE&C. This statement referenced the
same packing list, states that review and approval of
Mill Test Reports related to fabrication of the pipe
assemblies has been completed. The inspector requested
Packing list No.165-U or some means identifying the
This information
hangers listed on that Packing List.
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was not available.
The QA Engineer later provided a Certification of Compli-
ance from Bergen - Paterson which referenced an 155; pur-
chase order and stated that hanger material furnished
under that order is in accordance with the applicable
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governing codes and job specifications.
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Release for construction of spool piece 2-DH-124 and
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hangers BSH-88 and BSH-89 without complete documentation
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is considered to be a deficiency with respect to 10 CFR
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50, Appendix B, Criterion VII which states, in part:
"... Documentary evidence that material and equipment con-
form to the procurement requirements shall be available
at the nuclear power plant site prior to installation or
use of such material and equipment..."
3.
Chemical Requirements for Grout
Failure to verify confor=ance to ASME III, Division 2 for chloride
and nitrate content of freshly mixed grout had previbusly been
identifica as a Deviation.
(Inspection Report 75-08)
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The information shown below is for the grout material previously
used and still in use for tendon grouting.
a.
Admix
The admix used is Sika DP-23-3 (now known as Sikamix 122,
Grout Aid). The inspector examined a letter from Mr. Cordon
N. Scott, Consultant to B&R stating that this admix.has been
studied with respect to possible corrosion of the tendons and
that there need be no concern about the chemicals in the grout
for this application.
At the request of the inspector, the
licensee telephoned the chief chemist of Sika Chemical Corpora-
tion and was infor=ed that this admix contains no chlorides or
nitrates.
b.
Cement
A general analysis of the cement (Medusa) furnished by the
manufacturer shows chloride centent to be .003 .103 parts per
million (PPM). Test reports of cement sa ples taken period-
ically at the site during April - Nove=ber 1975, show chemical
content to be consistent with the general analysis.
A Pittsburgh
Testing Laboratory report of their analysis of a sample re-
cently taken at the site shows .01 PPM of chlorides and less
than .001 PPM of nitrates and sulphides.
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Water
The licenses stated that water used in the grout.is from a
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treated municipal supply and their routine analyses show
negligible amounts of chlorides and nitrates.
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This item is resolved.
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4.
Control of crimpine Tools
The inspector reviewed B&R Specification No. 2555-70, " Electrical
Equipment Installation."
Tables 1 and 2 of Paragraph 3.1.1.2.c, Section 16A of Division 16
and Paragraph 3.1.2 of Section 16D define the compressign require-
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ments for various sizes of cable and wire.
Paragraph 16D requires
compliance with the latest addenda of IEEE 336-1971.
Section 4 of IEEE 336-1974 requies that harduare shall be installed
in accordance with:
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Drawings,
b.
Manufacturers Instructions.
Installation Specifications (In this case B&R Specification
c.
2555-70)
and also that " Care shall be especially exercised in following the
provisions of the above documents for operations such as," ... In-
cluded in such operations is cable terminations. .
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Item 4 of Paragraph 5.11 of IEEE 336-1971 establishes the require-
ments for tightness of connections and f astenings.
The licensee
was unable to furnish to the inspector any
procedures for con-
trol, periodic calibration or visual ~ inspection of crimping tools
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used on cable and wire terminations which would be ensential for
compliance with the above requirements.
This item is unresolved.
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5.
Ir stallation of Cable Tray and Conduit Hanners
2 DC 87 for confor-
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During inspection of installation of conduit
marce to E6R Drawing No. 3174-1 Rev. 7, the inspector observed
white tags on the hangers indicating that the hangers were a
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Observation of installed cabic trays and
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tem 3orary installation.
other conduits shoved a large nurber of temporary hangers to
have been installed.
Approximately fifty such temporary hangers
have been int .alled on safety-related systems.
The QC check-off
lista showed that these cable trays and conduits
have been
released for cable pulling in accordance with appro' ed B&R Drawings.
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Howeser, hanger installation is in accordance with the sketches
been reviewed by B&R and uhich are
prepared by UE&C which have not
not shown on the released B&R drawings.
It was noted that the QC check-off lists do indicate that the
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Also the inspector noted that
hanger installation was temporary.
a proesdure (UE&C ECP/8-2 Rev. 13) ha.d been issued which permits
the use 6f temporary hangers on a limited basis. However, the
number of white tags observed on installed hangers indicates that
use of temporary hangers is the normal practice rather than an
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.occ.asional deviation.
GPU site audit report dated December 11, 1975 had identified the
same prcblem and the inspector uas inf ormed that a meeting had
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been scheduled for Deccaber 19, 1975 to resolve the apparent
contradiction in requirements.
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This item is unresolved.
6.
Temperature Conditi_oning of Cables
B&R Specification 2555-70 requires conformance to vendor installa-
The cable vendor's instructions
tion and bandling requirements.
for "Movenent, storage and installation" of cabic states in para-
to a warm area (70 F,
graph C " Move the reel, avoiding impact,
for eighteen (18) to twenty-four (24) hours is probably a good
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safe temperature) to condition the cable" prior to cable pulling.
QC procedures and check-off sheets do not.have any requirements
for cabic conditioning prior to cable pulling.
This item is unr-solved.
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Tolcrance-Incident Angle Ectueen Pine Socols
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inspection of decav heat oinc line.. it
During the
field wcld joint DH-128Q between spool piece No.
was noted that
DH 128 and Reactor Euilding penetration No. 525 vas a mitered
The inspector asked site QC personnel what the alignment
joint.
The inspector was
acceptance criteria were for mitered joints.
referred to the Burns and Roe
Specification No. 2555-75,
which addresses piping welding, fit-up and other cechanical
Division 15, Section ISD, Paragraph 4.2
component. installation.
inches and larger
states, " Erection of shop fabricated pipe 2
shall be in accordance with the Nuclear Power Piping Code ASSI
31.7 1969."
B&R Drawing No. 2077 Revision No. 7 provides details
tolerances, which are in accordance with Figure
of alignment
1-727-3.1 of ANSI E31.7 1969.
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in numerous instances
Discussions with site personnel indicated that
due to normal fabrication sequences,there was an angle between
the closure joint.
The inspector
centerlines of the components at
asked what angular tolerances were considered acceptable and when
The inspector was
a Deficiency Report was required to be issued.
provided specific acceptance criteria
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informed that the A/E had not
The licensee stated he would have the A/E
for such conditions.
evaluate this matter and provide acceptance criteria for site use.
This matter is considered unresolved pending evaluation and issuance
of more definitive acceptance criteria for these types of joints.
QC Procedures - Electrical Cables and Terminations
8.
The inspector reviewed UESC procedures as listed below for handling,
inspection and testing of electrical wire
storage, installation,
and cable.
Electrical Construction Procedure (ECP) ECP-3-2 for Receiving,
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a.
Storing, Handling and Installing Uire and Cable Rev.
dated December 1, 1975.
This procedure defines the QC require-
ments for inspection and record keeping during receipt.on site
storage, identification and docu=entation of qualifica' tion
tests.
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This procedure also establishes the requirements for cable
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handling and installation; inspection of conduit and cable
trays; cable identification, color coding, separatian and
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redundancy ; and wire.vay loading.
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TMI TP 250/2 " Testing and Checking of Mechanical and Electrical
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b.
Equipment" Rev. TCN-3 dated November 6,1975 ubich catablishes
the requirements for testing and terminations of cables.
QC Procedure QC-2-2 Rev. 6 dated May 14, 1975 which provides
c.
color
requirements for inspection of cable identification,
coding, termination and segregation and control of noncon-
forming materials.
Procedure ECP-5-2, Rev. 10, dated December 1, 1975." Receiving,
d.
Storage, Handling and Installations of Wire and Cable," which
establishes the requirements for wire-way separation, size,
type of cable, routing and protection including specification
of materials for fire barriers and wireway seals.
Procedure ECP-8-2, Rev. 3 dated August 29, 1974 " Quality Sur-
e.
veillance Plan," which defines requirements for inspection con-
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trol of changes to established specifications.
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Except as indicated in paragraphs 5 and 6 abcve, this item is
considered to be acceptable.
9.
Training and Qualification of OA/0C Personnel
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The inspector reviewed UELC Procedure QC-29-2, Rev. 3, dated April
18,1975 " Quality Control Personnel Training and Qualification."
This procedure requires that orientation and indoctrination of a
new employee be performed, evaluation of the employee's perf ormance
be made within 30 days and again within one year.
The inspector
examined personnel records of three UESC employees and found that
in cach case the orientation, indoctrination and performance evalta-
tion had been performed.
The inspector also examined audit records
of personnel training and qualifications as follows:
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14, 1975 which
GPUSC Audit Report 75-05 dated February
showed documentatica of evaluation of three QC inspectors
a.
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by a QC Engineering Report.
75-24 which documenced review of qualifica-
b.
GPUSC Audit Report
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tions of two Conam inspectors.
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75-14 dated April 5,1975 which reported
GPUSC Audit Report
that qualifications of NDT personnel were current and satis-
c.
factory.
This item is considered to be acceptable.
10.
Cable Pulling
E25VDC
The inspector witnessed pulling of four safety-related
supply system cables; cable' circuits and conduits are shown be-
low;
Cable Circuits 2DC-88 and 12DC-89 in Conduit
a.
Cable circuits 2DC-85 and 2DC-86 in conduit 2DC-85.
i
b.
the current of the
A calibrated current meter was recordingFor this pull, the current reading of the
cable pulling motor.
The maximum reading on the two
motor was requ, ired not to exceed 15 amps. Prior to pulling the cables
pulls witnessed wrs le. ; than 7 amps.through the conduit a vacuu
fish was pulled through to assure that no burrs were in the con-
procedure is in accordance with UE&C Procedure
duit.
This
Wire
ECP-3-2 for Receiving, Storing, Handling and Installing
10.
.
and Cable, dated December 1,1975 Rev.
This item is considered to be acceptable.
.
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11.
Piping Installation
The inspector visually inspected the main ranctor coolant loop pipe line
B-44-1 (RC pump 1B/A to the RPV) & the decay heat pipe line from reacto
It was
coolant pipe line A-32-1 to the No.1B decay heat pump.
found that the pipe lines, were run and connected as described in
the FSAR with redundant connections provided as co=mitted in the
Pipe spools pieces, fittings, and hangers (where cc=plete)
in accordance with isometric and
FSAR.
were installed
The following is an listing of pipes inspected,
layout drawings.
inspection.
responsible contractor, and drawings used for the
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a.
Line:
RC B-44-1 (RC Pu=p 1B/A to RPV)
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Contractor:
Babcock and Wilcox
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Applicable Drawings: " Location of Field Welds for Reactor
"
Coolant System"
.
Drawing No. 4467 Rev. 4
Change Notice No. 2832 Rev. 2
Comments :
It was observed that the reactor coolant pipe
B-44-1 was installed in accordance with the
applicable drawings and change notices.
Reactor
coolant pipe restraint CP-2 was installed and
modified in accordance with change notic.e 2832.
B&W Inspection Report documented visual inspec-
tion of restraint CP-2 as satisfactory (It.spected
9/12/75). B5W docu=entation (Field Construction
Procedure No. 13) found the installation of B-44-1
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acceptable.
.
b.
Line:
Decay Heat 12", (Hot Leg of "B" Generator to
Second Isolation Valve DR-V2)
Contractor: Babcock and Wilcox
Applicable Drawings: Piping Isometric Drawings 2-8-23,
2-8-24 and 2-8-25.
Hanger Sketch A-9459-FS-02-HS-DH HH-1
Figure 9.2-3 of the FSAR
Comments: The 12-inch diameter decay heat removal system
piping was installed in accordance with the
applicable sketches, drawings and FSnR cccmit-
ments. Pipe Hangers DHH-102, DHH-104, DHH-105
and DHH-107 vere located as shown on the appli-
cable drawings.
c.
Line:
Decay Heat (DH-V2 through Reactor Contain=ent
to Decay Heat Removal Pu=p DH-P-13)
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Centractor: United Engineers and Constructors
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Applicable Drawings: Piping Isometric Drawing 2-8-1, 2-8-2
3
and 2-8-3.
.
FSAR Figure 9.2-3
The piping was ' installed and welded between the
,
termination points outlined. Pipe hanger and
Comments:
support installation was not complete and no
attempt was made to verify hanger and support
All fittings and field welds were.
location.
installed and visual appearance of the finished
field weld surfaces was considered acceptable.
Cross connection between the decay heat pumps
DH-P-1A and DH-P-1B was provided for redundant
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operation.
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This item is considered to be acceptable.
12.
Observation of Field Welding
The inspector witnessed the field welding of three welds in three
systees and examined the as welded final condition and
reviewed the supporting documentation for one completed weld.
different
e
Welding operations observed and records audited indicated that the
velding was performed in an acceptable manner.
Table of Weld Joints Witnessed emd Data Reviewed:
a.
_C) served Conditions
'
Joint
Completed weld surface excmined'.
'
2-DH-171 (Decay Heat)
No undercuts or visual discon-
8" diameter, Nuclear
tLauities. Weld transition to
.
Class I
valve body meets 3:1 taper spec-
Schedule 160 pipe
ified by ANSI N31.7 - 1969.
Butt Weld
Reviewed quality records.
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Weld joint approximately one-half
2-DH-92C (Decay Heat)
Observation of the work
complete.
8" diameter, Nuclear
found the in. process veld appear-
Class II
ance acceptable. The craftsman
Schedule 40 pipe
was using the prescribed weld
Butt Weld.
filler material (3/32" ER 316L).
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Joint
Observed Condition
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The file used for veld bead
surface conditioning was marked
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for stainless steci use in
accordance with the site pro-
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cedures.
GTAW procedure was
used (UE&C Procedure No. 20
and 8), the inspector verified
that the welding amperage,
shield gas and purge gas were
in accordance with the proced-
ure. Weld History Record For=
7005 was completed co==ensurate
with status of the weld and as
required by QC-8-2 Revision 4.
2-NS-42 (Nuclear Services
Veld joint flush, welder in
Closed Cooling Water)
process of removing porosity
3" diameter
from surf ace to correct the
Schedule 40
condition prior to co=pleting
Butt Weld
the weld.
Filler metal 7018
electrode in use, was controlled
within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time span
(issue to use). UE&C weld -
Procedure No. I was in use and
~ was appropriate for base materials-
being welded.
139-C-6 (Make Up System)
Completed surface of first pass
"v Nuclear Class II
of fillet weld.
Shielding gas
Schedule 160
flow and filler metal 3/32" ER
Fillet Weld
30SL acceptable and in accord-
ance with UESC welding procedure
No. 20 and 8.
Weld History
Record available and co==ensurate
with status of weld.
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b.
Welder Qualification
I
the three
Reviev of UE&C and B&W site records showed that
welders performing the welds and the two welders who had
,
?
perforced the completed weld were qualified as required by
The welders whose
.
the applicable codes and site procedures.
qualification records were examined are as follows:
Welders Symbol
Contractor
Joint
2-DH-171
5049 and 3835
UE6C
2-DH-92C
5B
UE&C
2-NS-42
23-F
UE&C
139-C-6
20S
,
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NDE Personnel Oualification
c.
The inspector audited B&W site records documenting the qualif-
ication and annual vision checks for the two NDE examiners
It was found
who'had performed tests on joint 2-Dd-171
that the NDE personnel were properly qualified to perform the
liquid penetraat and radiographic examination of weld DH-171
i
(Level 11 SNT-TC-1A as applicable) .
Weld Material Certification - Joint DH-171
d.
The inspector audited QC records for ene heat of weld filler
metal (3/32" E 316; Heat No. 6343B) which was certified by
the requirements of AWS A5.4-69.
the manufacturer to meet
The manufacturer's chemical analysis and physical tests of
the re-
as deposited metal were reviewed and found to meet
quirements of AWS A5.4-69.
,
This item is considered to be acceptable.
13. Vendor Documentation
Lack of documentation on site to validate the integrity of certi-
the vendor facility had been
fication of acceptance inspection at(Inspection Report 74-06)
identified as an unresolved item.
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the
The inspector examined a report of a documentation review at
Documen-
Barberton and Lancaster, Ohio.
vendors plants at
-
tation examined pertained to the reactor internals, steam generators,
feedwater piping, reactor coolant surge and spray piping and control
?
Documentation included process sheets,
rod drive motor housings.
weld histories, welder qualification records, welding procedure
qualifications, weld inspection records, weld material
test re-
Th'e report
ports, NDE personnel qualifications and radiographs.
concluded that satisfactory evidence of adequate documentation
exists to support vendor certification for the equip =ent.
.
This ites is resolved.
14.
Seismic Integrity of CRD AC Breaker Cabinets
15, 1975 the licensee reported"a deficiency
.
By letter dated January
in design of the structural supports for the Control Rod Drive AC
Breaker Cabinets.
The lic~ensee stated that modification of these supports had been
completed and.the inspector examined the following documents:
27, 1975
Engineering Change Memo (ECM) No. 278, dated May
which provided details for a revised.sppport pad and attach-
a.
ments for this cabinet.
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b.
Concrete placement check out sheet daced October 30, 1975
which was signed off:.by Field QC on October 31, 1975.
sheet dated October 31, 1975
Inspector's concrete check out
c.
which referenced ECM No. 278.
.
d.
Concrete Status Report dated October 31, 1975.
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Reports of placement, batch plant inspection, curing and
e.
concrete cylinder tests.
This item is resolved.
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15.
Reactor Internals Handling Fixture
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A requirement for modification of the reactor internals handling
fixture had previously been identified.
(Inspection Report 75-01)
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The licensee stated that modifications to this fixture had b;en
made at the Barbert on, Ohio shop of B&W.
The inspector examined B&W Field Change (FC)-41 Rev. 1 dated April
3,1974 for modification of the Handling Adaptor Pendant and Field
Construction Procedure No. 245; Item 4.1.3 which showed that QC
had verified satisfactory completion of this work.
FC-41 provides for the modification authorized by B&R Field Change
Request No. 29.
,
This item is resolved.
16.
Qualified Release of Nonconforming Items
Lack of an adequate B&W procedure for control of " Qualified Release"
of nonconforming items had.previously been identified as an un-
resolved item.
(Inspection Report 75-02)
The inspector examined B&W Procedure 9A-107-1/C-6 Rev. I which
established a procedure for " Qualified Release" of nonconfor. sing
items and established a requircaent that approval of the Owner /
Agent be obtained in writing for release of such items.
.
This item is resolved.
17. NDE Persot ,el Oualification
Incomplete information and inconsistencies in eye correction
limitations had previously been identified as an unresolved item.
(Inspection Report 75-10)
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The inspector examined personnel qualification records of NDE
personnel particularly with respect to eye correction limitations.
.
Forms were complete for all. personnel and were found to be
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acceptable.
,
This item is resolved.
18.
UT Indications on CRD Motor Tubes
On August 24, 1975, the licensee reported observations of UT
indications on CRD motor tubes during pre-service inspection and
stated that a further 12vestigation sould be made.
The inspector examined a letter dated December 10, 1975.from Conam
Inspection, Incorporated which reported the results of a trip by
two Conam Level II inspections at GPU request.
The purpose of the trip was to analyze the UT indications noted
during examination of the CRD motor tubes and determine if these
indications were actual cefect conditions.
As a result of their analysis it was concluded that the indications
were due to irregular geometry of the part in sc=e locations and
enlarged grain structure in others but were not indications of
actual defect conditions.
'
The report did recoc=end certain modifications to the in-service
inspection procedure which the licensee said would be followed.
This item is resolved.
.
19.
Metal Coatines within Reactor Building
The licensee had reported by letter dat'ed August 26, 1975, defec-
tive coating on cable trays within the reactor building. During
a previous inspection (Inspection Report 75-13) the inspector had
reviewed corrective action which had been completed except for
completion of a review of all coatings within the reactor building.
The inspector examined:
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B&R Specification '555-85 Amendment No. 6 dated June 25,
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a.
1975 " Nuclear Area Cleaning and Coating of all Steel and
'
Equipment."
Field Change No. 2 to Construction Procedure CCP-12-2 which
b.
-
established the requirements for high tempetature aluminum
paint on certain NSSS equipment.
Inspection Reports No.
3549, 3550, 3559, 3560 and 3561
f 6r cleaning and painting of equipment within the reactor
c.
bu 1 ding.
17, 1975 from QC to QA_ stating that as
Memo dated December
d.
in-
date QC had inspected the coatings of all itect
of that
side the reactor containment requiring coatings and had docu-
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mented either a satisfactory or unsatisfactory inspection
.
report.
This item is resolved.
Voids in Exterior k'all of Fuel Handing Building
20.
(
By letter dated Nove=ber 14, 1975, the licensee had reported a
void in the south exterior wall of the Fuel Handling Building.
The inspector examined the following documents:
(DR1 No. 0522 dated October 16,19 75 which
Deviation Report
described the deviation and provided for B&R to issue an
a.
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Engineering Change Meme (ECM) for its repair.
ECM No. 3140 which provides a repair procedure using epoxy
in area 1 and an epoxy bonding agent plus concrete in area 2.
b.
Inspection Reports No . S-2903, S-2910 and S-2926 for grouting,
chipping, cleaning,and inspection of the work.
c.
The inspection report documented the satisfactory completion of
void repairs.
This item is res*olved.
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