IR 05000423/1978006
| ML19263C131 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/21/1978 |
| From: | Chaurdhary S, Mcgaughy R, Varela A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19263C127 | List: |
| References | |
| 50-423-78-06, 50-423-78-6, NUDOCS 7902070091 | |
| Download: ML19263C131 (8) | |
Text
-
-
-- -
-. -. -
-
-
.
U.S. NUCLEAR REGULATORY COMMISSION g
0FFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50 423/78-06 Docket No. 50-423 License No. CPPR-113 Priority Category A
--
Licensee:
Northeast Nuclear Energy Comoany P. O. Box 270 Hartford, Connecticut 06101 j
Facility Name:
Millstone Nuclear Power Station, Unit No. 3 Inspection at-Millstone Unit 3, Waterford, Connecticut Inspection conducted:
Novem er 28 - December 1, 1978 f
/2 7 7-Y Inspectors:
-
A.
,tp, eact r Inspector date signed
\\(
/2-20 - 73 A. A. Varela, Reactor Inspector date signed W (Laue/bani 12-20-78 j
S. K. Chaudhary, peactor Inspector date signed Approved by: k}il/i[(hw k/)w WWE 7. M. McGaughg @ief, Profec.t Section, date signed RC&ES Branch
,_
,
i Inspection Summary:
t Unit 3 Inspection on November 28 to December 1, 1978 (Report No. 50-423/78-06)
'
l Areas Inspected:
Routine, unannounced inspection by three regional based in-i spectors of quality verification records for containment structure concrete, and j
specifications / procedures governing containment structure work.
The inspectors also performed plant tour inspections, reviewed licensee action on previous
,
inspection findings, and performed follow-up action as necessary to resolve
.
questions which arose during the course of the inspection of the above areas.
'
The inspection involved 46 inspector-hours onsite by three NRC regional office i
based inspectors.
.
' Resul ts : No items of noncompliance were identified.
7902,070011
'
Region I Form 12 (Rev. April 77)
'
!
-
._.
.. - - -..
..
. - -.
._.
.. -
_
_
__.
.
.
.
i
.
!
,
DETAILS
_
l.
Persons Contacted Northeast Utilities Service Comoany
- T. W. Deshefy, Resident Civil Engineer
- 0. G. Diedrick, QA Manager
- K. W. Gray, Jr., Site Quality Assurance Lead
- S. R. Toth, Construction Site Mariager
- J. H. Szymanski, Construction Quality Assurance
- R. P. Zysk, Site Engineer Stone and Webster Enoineerino Corcoration
- 14. B. Anderson, Assistant Superintendent - Field Quality Control L. Barberie, Quality Control Engineer
- F. A. Belliveau, Boston Structural Engineer
- R. H. Lane, Superintendent of Construction
- W. MacKay, Resident Manager
- C. A. Marrs, Superintendent of Construction
- M. G. Pace, Assistant Suoerintendent of Field Quality Control L. Pathiah, Boston Mechanics Engineer
'R. Reams, Chief Materials. Supervisor
- G. G. Turner, Superintendent of Field Quality Control J. Whedbee, Welding Quality Control Senior Engineer l
- denotes those present at the exit interview.
2.
Site Tour The inspectors conducted a walk-through inspection of the construc-tion site and observed work in progress and preparations for con-
!
crete placement of the exterior containment wall.
The inspectors also examined installation of racks for piping in the containment annulus.
The inspectors interviewed craft personnel, supervision, and quality inspection personnel as such personnel were available y
in the work areas. Where more detailed inspection of an area was
!
conducted, the inspection scope and findings are described in other
paragraphs of the report.
I No items of noncompliance were identified.
!
_..
__ _ _
___
___
~_
__
__..
.
.
- - -
-
- - - -. _
.-- --
.. -
- -..
.
.
.
,
l
!
i
3.
Licensee Action Regarding Previous Inspection Findings
il (Closed) Unreso'.ved Item (423/78-05-03):
Identification of rein-forcing steel heat #207Cl34 rejection.
The inspector examined
documents which identified that two #18 reinforcing steel bars of q
labelled grade 60 were incorrectly included with the shipment of special grade 50 bars of heat #207Cl34.
The documentation showed
that the material had been returned to the supplier along with 14 bars which had been similarly provided with heat #2078320. The related corrective action documentation included Stone and Webster request for supplier corrective action to prevent recurrence, and Bethlehem Steel Company response to take corrective steps regarding activities in the Steelton Fabricating Shop.
Additionally, Stone and Webster has included verification of reinforcing steel grade marking as a check point for quality control cadwelding inspection.
These actions appeared appropriate to the circumstances.
In addi-tion to documents previously examined as listed in IE Inspection Report 50-423/78-05, the inspector reviewed the following specific documents:
.
Nonconformance Reports N&D - 6881 dated October 6,1978
--
N&D - 6610 dated December 17, 1976 QA Inspection Reports #S8050595, #S6008888 and #8050975
--
Certificate of Conformance Release #643 dated May 18, 1978
--
Stone & Webster Letter #SWVL-2010 dated September 20, 1978
--
Stone & Webster Letter #NESF-1945 dated March 10, 1977
--
Bethlehem Steel Corporation Letter dated October 9, 1978
--
S&W Report of Meeting dated December 29, 1976
--
S&W Interoffice Correspondence dated December 22, 1976
--
S&W Interoffice Correspondence dated December 29, 1976
--
S&W QA Tensile Test Report dated December 27, 1976
'
--
-1 S&W Revised Inspection Report Form for Cadwelding dated
--
August 7,1978
'
4
.. _ _
....m._
..
..-
.
.._ -.-
-
.
-.
_.
_ _ _ _ _... _.
_.. -
_
.
.
.
,
4
,
I (Closed) Unresolved Item (423/78-05-01):
Possible encroachment on pipe minimum wall in area of overgrinding on nozzle #7 of a boric acid tank.
The inspector examined licensee inspection and evaluation reports regarding the apparent undercut /overgrinding, which showed that the area in question has been weld repaired, reinspected and found acceptable.
The inspector examined the following specific documents relative to the above:
S&W Inspection Report IR-X8020013
--
S&W Stop Work Directive dated September 1,1978
--
RECO letter to S&W dated October 24, 1978
--
I RECO Defect Oisposition Reports #204-4 and #204-5
--
I 4.
Containment Structural Concrete - Records
!
-
l The inspector reviewed pertinent work and quality related records
associated with concrete placements previously observed for the
.i structural concrete exterior wall of the containment building.
The pump placement numbers selected for review are C-3102 and C-3107 for work performed August 10 and 11, 1978.
The inspector deter-mined that the records reflect work acccmplishment according to criteria identified in the following:
-
I Millstone Nuclear Power Station Unit 3 PSAR Chapter 3, its
--
referenced codes and standards and PSAR Chapter 17, Project Quality Assurance Program.
!
Job Specification #C-999, Placing Concrete and Reinforcing
--
.i Steel, Revision 1, Addendum B, April 28, 1977.
Job Specification #C-281, Mixing and Delivering Concrete.
--
,
S&W QC Instructions and Procedures - QAD-10.2,10.8,11.2 and
--
14.3, and QS-10.12,10.13,11.11 and 14.2.
-i S&W Field Construction Procedure No. FCP-267, for Reactor
!
--
Containment Exterior Wall Placements.
i t
,
--.--..,%.
w --
e-
--
.
w-e
--
- - -
.
-
-
_
--
. - - -.. - -.. -
-. -.
.
.
!
~
i
!
,
!
j The inspector reviewed documentary evidence and verified work accomplishment consistent with applicable requirements in the following areas:
a.
Preplacement Preparation - location preparation and inspection sign-off were reviewed in QCIRS #S8000990 and S8001047.
b.
Delivery and Placement - mix specified was delivered and placed, records of batches delivered, required tests and inspection records relative to the placements were reviewed in QCIR #S8000991 and supporting attachments, c.
Qualifications of Inspection Personnel - personnel records, training and qualification certificates of six ouality control engineers / inspectors were reviewed and observed to fullfill requirements of ANSI 45.2.6 as required by S&W Quality Standard QS-2.12 for rebar installation and cadwelding,,
concrete inspection (pre-placement, in-process and post place-ment), batch plant and materials testing.
d.
Curing of Concrete - temperature, fann removal and inspection records reviewed in QCIR 58000999.
e.
Rebar Splicing - as-built drawings FSK-S-506-2 and 538-1 I
were reviewed and a random selection of ten cadweld splices
was made to provide traceability, retrievability and complete-ness of QC inspection records on qualifications of process
-
and crew, sampling for in-process testing and rebar material
-
certification.
!'
f.
Concrete Materials - records confirm materials meet specifi-
!
cations; inspection records on control of material, receipt and in-process inspection for cement, aggregates, water and
'
!
admixtures provided verification that materials meet specifi-
!
cations.
!
g.
Batch Plant Operation - production records and inspection
,
'
QC reports for placements of August 10 and 11 totaling 370 cubic yards of 3,000 psi concrete were reviewed; batch plant
'
automatic print-out records of ingredient weights representing-i
!
79 batches were observed complete and legible with required verification and acknowledgement by S&W batch plant inspector; S&W batch plant inspection reports on calibrations and
'
maintenance, QCIRS #58000319 through #S80001058 dated April
!
through August 1978 were observed in conformance to NRMCA l
and ASTM C-94 required by job specifications.
!
,
_. - - _,
. _. _ -. -.
_ _-
_ _. _. _..
. -. _.
._ _
- -.
_.
..
.
-
--
--
.-
.. _. - - -
.
-
,
i
I
'
,
h.
Deviation Reports - NRCs #6857, -69, -75, -78, and #6884 re-garding cadwelding, reinforcing steel, overslump concrete, and i
excess fines in coarse aggregate were observed complete,
'
legible, that corrective action was specified and proper approvals were identified on the reports.
An engineering change #PS-1955 was also examined, regarding rebar spacing questions raised by the inspector, which appeared to be pro-cessed acceptably.
l
!
i.
Audits - NUSCO audit reports #A40410, -21, -37, -40, -88 re-l garding concrete placement, batch plant operation, concrete l
testing, reinforcing steel placement for May 1977 through t
October 1978 reflected audits per ANSI-N45.2.12 guidelines.
Associated audit / survey schedule and follow-up reports dated
.
November 29, 1978 and audit follow-up records attached to audit reports showed contractor corrective actions included steps to prevent recurrence, wnere warranted.
S&W audit report #16, and nonconfonnance reports NSD-6755 and 6884 reinforced this conclusion.
No items of noncompliance were identified.
l 5.
Reactor Coolant Pressure Boundary Pice-Work Activities - (Storace
On-Site)
,
I The inspector observed storage of stainless steel reactor coolant
pressure boundary piping inside vented temporary greenhouse type i
structures, and examined a related Westinghouse October 9, 1978 report of site storage inspection on October 3-4, 1778.
The in-
'
spector observed corrective action in response to the Westinghouse
inspection and viewed the interior of three pipe spools, observed l
interior apparent condensation moisture, as had the Westinghouse
!
representative.
The licensee appears to be in routine communication
!
with the vendor regarding measures to eliminate condensation.
f The inspector observed a 5/32" deep by 1" diameter grinding blemish on a nozzle of stainless steel pipe spool number PC-LP2-CL2 (Tubeco
Incorporated).
The inspector inquired regarding. acceptability of
.
this item, and reviewed available relevant documentation.
Documen-
'
tation was not on site to permit determination of whether or not I
the defect was identified, evaluated, and accepted, other than the general certificate of conformance provided by Westinghouse.
The Stone and Webster site OC representative stated that they had
.
.
t
..
-
- %_,
--
-
. - -.
-
-
-
. _ _.-
- -... -..
--..
-
.
I
!
!
l
l measured the inperfection and evaluated it for encroachment on pipe minimum wall specified on design drawings, and found it acceptable.
The inspector had no further questions at this time.
The inspector examined the following documents relative to the above:
Receiving Report MRR-78-1295
--
Inspection Report IR-8050355
--
Quality Release QR #39486
--
Deficiency Notice DN-09167
--
Data Report NPP-1 for LP2-CL2
--
,
No items of noncompliance were identified.
6.
Containment Structure Soecifications/ Procedures The inspectors interviewed Stone & Webster responsible engineers who were onsite during this inspection.
Specification or pro-
,
cedure requirements were discussed relative to the following:
i l
, Reduction of rebar minimum spacing due to rebar spreading
--
l around penetrations.
l l
Practicality of meeting PSAR Section 3.8.2.9 requirements
--
i regarding containment structural integrity test crack pattern
!
mapping, relative to schedules for encasement of the lower
!
wall within the concrete fill or ring girder.
i i
Properties of compressible material, used for seismic separa-
--
!
tion of structures, to accommodate compression by plastic i
concrete.
!
I Engineering action in these areas appeared acceptable, although
decisions regarding crack pattern mapping are pending further
'
review.
(423/78-06-01)
,
No items of noncompliance were identified.
'
,
.
.. -
.... - -. -
-
..
-.
.-
- -.
- - - -.
. -. - - -
. - - - - _.
.. _ -. -
.
.... -_.
._
.. -
,...
i i
.
I 7.
Management Interview At the conclusion of the inspection on December 1, 1978, a meeting was held at the site with representatives of the licensee and contractor organizations. Attendees at this meeting included personnel whose names are indicated by notation (*) in paragraph 1.
The inspectors sumarized the results of the inspection as described in this report.
I i
i i
!
i
!
l
!
t i
i t
l i
i
$
.
.-
-
... -,.
.