ML19220A915
| ML19220A915 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1975 |
| From: | Folsom S, Gage L, Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220A903 | List: |
| References | |
| 50-320-75-02, 50-320-75-2, NUDOCS 7904250089 | |
| Download: ML19220A915 (16) | |
See also: IR 05000320/1975002
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IE:I Forn 12
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(Jan 75) (P.cv)
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U.S. liUCLEAR RECULATORY CO::MISSIO:1
0FFICE OF II;SPECTIC:t A ;D DIFORCEME;T
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.RECION I
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50-320
50-320/75-02
Dodet No.
IE Inspection F2 port 2:o:
CPPR-66
l' tr p lit n Ediscn Cenpany
Licence !!o:
Licensee:
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Box 542
pg
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Reading, Pennsylvania
19603
A
liiddletown Dauphin County, Pa. (Three liile
Safe p ds
Location:
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Island 2)
Croup:
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Pk'R, 871 INe (B&W)
Type of Licensec:
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Routine, Unannounced
Type of Inspection:
February 20-21, 1975
Dates of Inspection:
J nuary 22-23, 1975
Dates of Previous Inspection:
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Reporting Inspector:
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Seth A. Folsem, Reactor Inspector
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Accompanying Inspectors:
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L. W. Cage, ReaQr Inspect %f '
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L. Narrow, Reacter Inspecf r/
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Date
NONE
Other Acco=panying Personnel:
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O[2,)
Reviewed By:
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R. F. Heishman, Senior Reactor Inspector
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SUmiARY OF FINDINGS
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Enforcement Action
A.
Items of Moncemoliance
1.
Deficiencies
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Contrary to the requirements of 10 CFR 50, Appendix B,
stored outdoors on
a.
Criterion V, power and control cables,
partially filled reels, were not protectively sealed in
(Details,
accordance with vendor supplied procedures.
Paragraph 2)
Contrary to the requirements of 10 CFR 50, Appendix ? ,
b.
Criterion XIII, asbestos-braided instrumentation cables
were stored in areas unprotected from rain, snow, and
ground water.
(Details, Paragraph 3)
Contrary to the requirements of 10 CFR 50, Appendix B,
Criterion XV, nonconforming (scrapped) cabic was stored
c.
(De-
in the same area as conf orming (accepted) cabic.
tails, Paragraph 4)
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B.
Deviations
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None
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licensee Action on Previous 1v Identified Enforcement Matters
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The f ollowing previously identified enforcement matters were resolved
during the inspection:
Embedment of temporary polar crane support towers in permanent
1.
(Details, Paragraph 8)
containment concrete.
(Details ,
Heating of reinforcing steel to unknown temperatures.
2.
Paragraph 9)
Design Channes_
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None Identified
Unusual Occurrences
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None Identified
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Other Significant Findines
A.
Current Find'ncs
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1.
Unresolved It ems
The Site Quality Control Procedure No. QC-17-2 " Control
a.
of Nonconf orming Conditions" did not refenence the
architect-engineer's " Vendor Data Status Report" which
is used in conjunction with the procedure to determine
acceptability of vendor documentation.
This item is
considered unresolved.
(Details, Paragraph 13)
The B&W procedures permit inst'allation of nonconfo' ming
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b.
items, " Caution" tagged, with the concurrence of the
Field Project Engineer, Field QC Supervisor, and the
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licensee.
For items which UE&C has QC responsibility " Qualified
Release" is controlled by Procedure QC-17-2.
For items
which B6W has QC responsibility t'iere are no written re-
quirements established to control " Qualified Release".
This item is considered unresc1ved.
(Details, Paragraph 5)
f
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Acceptable Items
2.
The f ollowing items were examined and, with the exception of
the "ltems of Nonec=pliance" and " Unresolved Items" listed
above, are. considered to be acceptable.
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Procedures for control of nonconforming piping items.
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a.
(Details, Paragraph 5)
b.
Procedures for quality assurance / quality control of
piping installations.
(Details, Paragraph 7)
Conformance of NDE techniques, personnel, record keeping,
c.
and equipment to applicable codes and standards.
(Details,
Paragraph 14)
d.
Procedures f or calibration of nondestructive examinations
and welding equipment.
(Details, Paragraph 14)
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Procedures for control of weld materials.
(Details,
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e.
Paragraph 14)
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f.
Quarantine of nonconforming caterials.
(Details,
Paragraph 4)
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Status of Previously Renorted I'nresolved iteen
The following previously identified ite= were resolved during
the' inspection:
s.
a.
Splice plate dropped into reactor pressure vessel.
(Details, Paragraph 10)
b.
In-t rans it dacage to reactor coolant nozzle.
(Details,
Paragraph 11)
c.
Apparent below-standard concrete in containment structure.
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(Details, Paragraph 6)
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d.
Periodic battery check acceptance criteria.
(Details,
Pacagraph 12)
Management Intervieu
The management interview was held at the site on February 21, 1975, with
the following personnel in attendance:
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General Public Utilities Service Company
Mr. R. F. Fenti, Quality Assurance Auditor
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Mr. G. L. Kopp, Quality Assurance Auditor
Mr. S. Levin, Proj ect Engineer
Mr. P
A. Levine, Quality Assurance Auditor
Mr. G. L. Roshy, Quality Assurance Engineer
Mr. M. J. Stromberg, Site Quality Assurance Auditor
Mr. J. H. Wright, Resident Civil Engineer
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Babcock & Wilcox
Mr. B. E. Treadway, Proj ect }bnager
Mr. R. J. Kunz, Quality Control Supervisor
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United Encineers and Constructorr
Mr. V. E. Cichocki, Coordinating Superintendent, Quality , Assuranec /
Quality Centrol
Mr.
C. W. Hunter, Electrical Supervisor
Mr. D. C. Lambert, Field Supervisor, Quality Control
Eurns and Roe
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Mr. T. R. Block, Site Lead Quality Assurance Engineer
Mr. C. T. Harper, Jr. , Site Proj ect Engineer
The following was discussed:
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1.
The inspector discussed the " Criteria for betermining Enforcement
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Action and Categories of Noncompliance with AEC Regulatory Require-
cents - lbdifications", dated December 31, 1974.
The licensee
acknowledged this information.
2.
The inspector stated that three items of nencompliance, each
categorized as a deficiency, had been identified at this inspection.
It was observed that power and control cables, stored outdoors
a.
on partially filled reels, were not protectively sealed in
accordance with vendor-supplied procedures.
This is considered
to be a violation of Criterion V of Appendix B,10 CFR 50.
(Details, Paragraph 2)
b.
It was observed that asbestos-braided instrument cables were
stored in areas unprotected from rain, snow, and ground water.
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This is considered to be a violation of Criterion XIII of
App en dix B.
(Details, Paragraph 3)
It was observed that nonconforming (scrapped) cable was stored
c.
in the same area as conforming (accepted) cable.
This is con-
sidered to be a violation of Criterion XV of Appendix B.
(Details, Paragraph 4)
The licensee acknowledged this inf or=ation.
3.
The inspector stated that the following items were considered
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unresolved:
For items which BUJ has QC responsibility, there are no written
a.
requirements established to control " Qualified Release". (Details,
Paragraph 5)
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Procedure No. QC-17-2 did not ref erence the architect-engineer's
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" Vendor Data Status Report".
(Details, Paragraph 13)
b.
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The licensee acknowledged this information.
the f ollowing previously identified items
4.
The inspector stated that
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had been resolved:
(Details,
Splice p3..tc drepped into reactor pressure vessel.
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a.
Paragraph 10)
(Details,
In-transit damage to reactor coolant no::le.
b.
Paragraph 11)
Embed =ent of tecporary polar crane suppcrt towers in percanent
c.
(Details, Paragraph 8)
concrete.
structure.
Apparent below standard concrete in containment
d.
(Details, Paragraph 6)
(Details,
Periodic battery check acceptance criteria.
e.
-Paragraph 12)
(Details,
Heating of reinforcing steel to unknown te=peratures.
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f.
Paragraph 9)
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The licensee acknowledged this inf ormation.
The inspector stated that the items listed below had been examined
during the inspection, and were considered to be acceptable, except
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5.
for the previously stated items.
(Details ,
Procedures f or control of nonconforming items.
a.
Paragraph 5)
' Procedures f or quality assurance / quality control of piping
b.
installation.
(Details, Paragraph 7)
Conf ormance of NDE techniques, personnel, record keeping, and
(Details,
equipment to applicable codes and standards.
c.
Paragraph 14)
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Procedures f or calibration of nondestructive examination and
d.
welding equipment.
(Details, Paragraph 14)
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Procedures for control of weld materials.
(Details,
c.
Paragraph 14)
(Letails, Paragraph 4)
Quarantine of non-conforning caterials.
f.
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'Ihe licensee acknowledged this inf ormation -
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DETAILS
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1.
Persons contacted
General Public Utilities Service Compan_v
Mr. R. F. Fenti, Quality Assurance Auditor
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Mr. C. L. Kopp, Qual ty Assurance Auditor
Mr. S. Levin, Proje. En gin eer
}k. P. A. Levine, Q iity Assurr ce Auditor
Mr. G. L. Roshy, Quality Assurs' s En-ineer
Mr. M. J. Stremberg, Site Qualaty Assur cica Auditor
ik. J. H. Wright, Residant Civil Engineer
Babcock and Uilcox
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Mr. R. J. Kunr, Quality Control Supervisor
Mr. B. E. Treadway, Proj ect Manager
United Encineers and Constructors
Mr. V. E. Cichocki, QA/QC Coordinating Superintendent
Mr. J. P. Fleming, Chief Test Engineer
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Mr. C. W. Hunter, Electrical Supervisor
Mr. D. C. Lambert, Field Supervisor, Quality Control
Mr. F. F. Long, Assistant Field Supervisor, Quality Control
Burns and Roe
.Mr. T. E. Block, Site Lead Quality Assurance Engineer
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Mr. G. T. Harper, Jr. , Site Project Engineer
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2.
Protective Seals on Power and Control Cables
The inspector examined the storage conditions of the approximately
100 partially filled reels of power and control cables lef t over
from the construction of Unit No. 1, for use.on Unit No. 2.
The
cables were stored outdoors, with the cable ends nonunif ormly
protected with electrician's or friction tape.
The constructor's Procedure ECP-3-2, Revisicu 6, Paragraph 4.4.4
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sta+cd "The ends of all cable / wire stored outside shall be scaled
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to prevent the entrance of moisture". No method for scaling the
cable was provided.
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The cable Purchase Order No. C-0084, and ref erenced Specification
No. 2555-68, Amendnent 5, Paragraph 4.0 states " Contractor shall
furnish instructions on the reccarended methods for the storage
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of the cables".
Tne contractor provided the licensee, in Engineering Memorandum
N o .. 129, dated September 16, 1971, with scaling instructions which
included stripping the cable ends crd sealing with four layers of
insulating tape f ollowed by two layers of f riction bape and one
layer of vinyl electrical tape.
Failure to f ollow this sealing procedure on t _ cable ends is con-
sidered to be a deficiency in noncompliance with Criterion V of
10 CFR 50, A.ppendix B.
3.
12ck of Protection f rom Water f or Instrument-tion Cables
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The inspector examined the instrumentation cable storage conditions.
The cable was stored in a shed whose f our sides were protected by a
wide-cesh wire f ence which af forded no protection from rain or
snow. Four reels of Type 15FI asbestos-braided instru=entation
cable were f ound :tn an area reserved f or power cable.
Tnese were
covered by a tarpaulin, but were in direct contact with the unpaved
ground, and were exposed to ground water.
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These storage conditions were not in accord with' the requirements of
Specification No. 2555-106, Amendment 4, Paragraph 3.8.2.4, and
Specification No. DS38948-1, June,1971.
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Failure to store the instrumentation cable properly is considered
to be a deficiency in noncompliance with Criterion XIII of 10 CFR
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50, Appendix 3.
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4.
Nonsenrecation of Scrapped Cable
The inspector examined the outdoor cable yard used for storage of
conforming power and control cable,
Several reels of nonconforming
(scrapped) cable were found among t.he reels of accepted cable with
nothing in evidenca to identify the cable as nonconforming.
The f ailure to prevent inadvertent use of nonconiorming material is
considered to be a deficiency in noncompliance with Criterion XV of
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Installatien of Nonconformine Items
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for control-
The inspector examined the f ollowi g QA/QC procedures
1 Lng the release of nonconforming items.
B&W Procedure 9-QA-13/C-6 dated November 4,197410 dated Dec
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a.
UT&C Pr ocedure QC-17-2 Rev.
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items
b.
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Section 3 of Procedure 9-QA-13/C-6 requires that nonconf.or
be tagged with a " Reject"
" tag.
The use of
items if they are tagged with a yellcw "Cautionce of the B&W Field
the " Caution" tag requires documented concurren
l of the
Project Engineer and Field QC Supervisor as vell as approva
,
licensee.
f ming
Procedure QC-17-2 provides for " Qualified Release" of noncon or
QA lbnager
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ites if approved by the licensee Site Project Manager,Such items are taggad w
and the A-E Site Project Manager. Category I Qualified Release
h permit
Section IV of this procedure establishes conditiens whic
Qualified Release of nonconforming items.
2
The inspector asked if the cenditions of Section IV of QC-17-The A-E
applied to B&W installed equipment.that they did apply to such
d r control by
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f the equipment
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the A-E's QC group but did not apply' af ter release o
to B&W., ner to materials purchased direc;1y by B6W.
.
This item is unresolved.
Apoarent Below Standard Concrete in Centain=ent
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break
The inspector examined the concrete rest cylinde
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t con-
h.
The data now
crete which appeared to be sub-standard in st*cngt
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break results were within the requirements of th
This item is resolved.
applicable code.
Eoundary Piping
QA/0C Procedures _ - Reactor Coolant Prespr71
7.
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fied
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The inspector examined selected QA/QC proc
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Pressure Boundary piping and the architect-engineer for conformance
to the require =ents of the licensee's application.
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a.
The ELW Quality Assurance P.anual describes the quality program
of this contractor sad establishes the policy governing per-
f orrance of quality related activities.
It provides for
independence and f reeden of action of QA/QC personnel including
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stop work authority and establishes the require:ents for per-
f ormance and documentatien of audits.
This ite: is considered
to be acceptable
b.
The foll.owing BLU Quality Control Procedures were examined:
No. 9A-117-1/C-6 "St ora ge Requirements"
No. 9A-ll7-2/C-6 ""aterials Control"
No. 9A-ll7-2/C-6 " Preventive Maintenance"
No. 9A-125/C-6 " Field Construction Procedure for Installation
at Pipiny Systems"
No. 9A-126/C-6 " Procedures f or 11and. ling Deviation to Field
Construction Procedures"
No. 9A-128/C-6 " Cleanliness Requirements"
nese procedures provide requirements for
.e
.'ing control
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records; Heat treatment activities; weldag t epairs; receiving
inspection and storage; work perfor=ane.e; and witressing and
inspection of work performed f or lascallation of tce RCPn
P ping.
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c.
The A-E's QC procedures listed be.',ov were examined:
QC-9C-2 " Nuclear Steam Supply Syt t . 2 Installation"
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QC-2-2 " Receiving Inspection"
QC-3-2 " Storage Control"
QC-7A-2 "QC Surveillance Plan"
nese procedures provide the require =ents for receiving inspec-
tion and storage of material for the RCPB piping and for sur-
veillance of the work by B&W on this system.
H is item is considered to be acceptable.
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8.
Embed:ent of Tc porary Crane Support in Permanent Conc re t e
The inspector exacined the docume: tation relating to the embedment
of the temporary crane support in the containment structure con-
trete.
This included change orders, drawings, concrete placcren*
sheets, and quality centrol records.
In addition, a Division of
Reactor Licensing letter to the licensee, dated Februar;
7, 1975
stated, in part ". . .we find that the structural inte.grity of the
concrete walls containing the c bedded structural steel has not
been impair ed. . . ".
This itcs is resolved.
9.
Heatinc
.f Reinf ercine Steel to Unknown Tenocratures
The licensee had cut off 6 inche: from the ends of twelve reinfore-
ing steel bars to re=ove the portions which had been subjected to
uncontrolled heating.
The inspector examined these bars, and the
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No.
supporting docunentation which included "UELC Deviation Report
0386", dated December 26, 1974.
This item is resolved.
10.
Solice Plate Droceed into Reactor Pressure Vessel
The inspector examined the following docu=entation relating to the
investigation and NDE on the reactor pressure vessel interior:
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B&W letter to licensee, October 8,1972
enclosing report on
e
a.
UT and ET examination of reactor vessel,
b.
B&W " Report of Inspection", Procedure No. BLI-2, Reactor
Vessel Cladding, September 26, 1972, which included details
of UT, couplant, calibraticn, and gage blocks.
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This item is resolved.
11.
In-Transit Damare to Reactor Coolant Piping
The inspector examined the following documentation relating to the
repair and NDE of the weld prep of the outlet pipe assembly damaged
in transit.
B&W Contract Variation CV 206-23 FEV, November 28, 1972, which
a.
included sketches of repair areas.
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b.
B&W Ictter to licensee, December 14, 1972 which stated in part,
"This letter . . . certifies that the f abrication. . . has been
co=pleted. Based on the above, QC release is granted on the
above referenced component".
This item is resolved.
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Periodic Battery Check Acceptance Criteria
12.
he
The inspector examined the newly r tvised instructions regarding tinstructions
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The
interpretation of battery check readings.f or exampic; raximum volta ge variation
(not less than 1.220).
frequency of readings,
(plus or minus 0.04 volts), snecific gravity
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This item is resolved.
s.
in Site Precedure for Nenconformances
13.
Reference
The inspector reviewed the use of Site Quality Centrol Procedure
The latest
No. QC-17-2, " Control of Ncnconf orning Conditf or.s".Fevision 10,, Dec
revision of this precedure,
Report",
not reference the architect-engineer's " Vendor Data Status
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Pro-
which is prepared in accordance with the architect-engineer sis used in conjunctio
This report
j ect Procedure No. SP-84-19.with the procedure to determine the ac
f vender data.
This itet is resolved.
Nondestructive Exanination OA/QC Procedures
14.
The inspector examined the f ollowing QA/QC procedures relating to ,
applicability
NDE techniques, persennel, records, and equipment;
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to codes and standards; calibration of NDE and welding equ pecn ,
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velding materials control.
B&W QC Manual - Procedures all refer to " Applicable Fabrication
Code - ASME,Section III, 1971 Edition".
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a.
B&W "NDT Personnni Certification Record" - listing " Level of
Test" f or example. Level II, SNT-TCIA Supplement A (CP-5A)
b.
97-101/C-6, Revision 0,
B&W " Calibration Control Progran No. periodic inspection of gages
c.
10, 1973",
October
instruments as required by the ASME Code.
9A, 144,
B&W " Preventive Maintenance for NDE dquipecnt" No.
MT equipment
d.
C-6, Revision 0, October 1,1973", RT equipment,
cleaniag and maintenance.
O, and
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B&W " Control of Weld tutcrials" 9A-107-1/C-6, Rev.
e.
9A-158/C-6, Rev. 1.
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These procedures were considcred acceptable.
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