ML19249A665
| ML19249A665 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/20/1979 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249A662 | List: |
| References | |
| 50-339-79-33, 50-404-79-05, 50-404-79-5, 50-405-79-05, NUDOCS 7908240118 | |
| Download: ML19249A665 (6) | |
See also: IR 05000339/1979033
Text
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UNITED ST ATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIET T A ST., N W . sulT E 3100
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AT L ANT A GionGI A 30303
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Report Nos. 50-339/79-33, 50-404/79-05, and 50-405/79-05
Licensee: Virginia Electric and Power Coepany
P. O. Box 26666
Ricleand, Virginia 23261
Facility Name: North Anna Units 2, 3, and 4
Docket Nos. 50-339, 50-404 and 50-405
License Nos. CPPR-78, CPPR-114 and CPPR-115
Inspection at North Anna site near Mineral, Virginia
Inspector:
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C. R. McFarland
Date Signed
Approved by:
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J. C. Bryant
ate Signed
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SUM.MRY
Inspection on May 29-31, 1979
Areas Inspected
This routine, unannounced inspection involved twenty four inspector-hours onsite
in the areas of 10 CFR 50.55(e) items (Units 2, 3 and 4), IE Bulletins (Units 3
and site QA and QC organization and responsibilities.
Results
Of the three areas inspected, no apparent items of nonccepliance or deviations were
identified.
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DETAILS
1.
Persons Contacted
Licensee Employees
- P. G. Perry, Senior Resident Engineer
E. R. Bane, Supervisor, Construction QA
- P. A. Slater, QA Engineer
- M. A. Harrison, QC Engineer
Contractor Organization
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Stone and Webster Engineering Corporation (S&W)
A. A. Dasenbrock, Resident Manager
- C. A. Goody, Superintendent, Construction
- R. L. Spence, Superintendent, Field Quality Control (FQC)
J. Howard, Senior FQC Engineer
- B. R. Hall, Senior FQC Engineer
A. Clawson, Jr. , FQC Engineer
F. P. Carchedi, FQC Engineer
W. Davis, Senior QC Inspector
R. Ferguson, Senior QC Inspector
W. G. Slocumb, Senior QC Inspector
R. King, Electrician
D. Mueller, Supervisor, Construction Acceptance & Test (CAT)
Klockner-Moeller Corporation (K-M)
R. Geissler, Project Engineer
NRC Resident Inspector
M. S. Kidd
Other licensee employees contacted included several construction craftsmen.
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on May 31, 1979, with
those persons indicated in Paragraph 1 above.
The VEPC0 cenior resident
engineer confirmed that the present schedule for loading fuel was June 26,
1979 and that the construction permits for Units 3 and 4 have been extended
for five years. The inspector explcined that the reporting of new 10 CFR 50.55(e) items for Unit 2 would be documented in the NRC Resident Inspector's
report.
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3.
Licensee Action on Previous Inspection Findings
(Open) Item 50-404/405/79-02-01 Humidity in internals of components in
storage, Units 3 and 4.
The inspector reviewed documentation relative to
the Babcock and Wilcox Company's (B&W) concern for the deficiencies in the
storage of the reactor vessel and internals, the steam generators, other
reactor coolant system components, and other safety related components
supplied by B&W.
Discussions with the VEPC0 senior resident engineer indicate that in June 1979
VEPC0 will begin to construct new warehouses (40,000 square feet of level B
and 40,000 square feet level C) for the storage of equipment for Units 3
and 4 as part of a program to correct the deficiencies cited by B&W and the
concern identified in Region II reports 50-404/79-2 and 50-405/79-2. This
item was inadvertently identified as 50-404/78-06-01 and 50-405/78-06-01 in
that report; the correct numbers for the unresolved items are 50-404/79-02-01
and 50-405/79-02-01.
Construction of the warehouses is scheduled to be
completed in November 1979.
6.
Unresolved Items
Unresolved items are matters about which more information is required to
determine whether they are acceptable or may involve noncompliance or
deviations. Two new unresolved items identified during this inspection are
discussed in Paragraph 7.
5.
Licensee LJentified Items
VEPC0 has reported a number of items to Region II in compliance with IC CFR
50.5s(e) and/or 10 CFR 21, and the inspector reviewed the items noted below
and the supporting documentation, and discussed the items with responsible
staff during the inspection.
a.
(Closed) Items 50-339/78-36-02 Spare Pipe Penetretions, Unit 2.
The
inspector reviewed the VEPC0 final report dated February 1,
1979,
serial number 661 B, the interim reports dated November 22, 1978 and
December 20, 1978 and documentation relative tc !.ngineering and Design
Coordination Report (E&DCR) 2519.
S&W has installed welded caps on
the outside containment ends of all 29 spare penetrations in accordance
with the VEPC0 commitment in FSAR Section 6.2.4.3.
The inspector
observed the following penetrations as typical examples of the various
designs of caps for the various sizes (1/4, 3/4, 2, 4 and 6 inches
diameter pipe) materials (carbon steel and stainless steel) and wall
thickness (schedule 40, 40S, 50, 80S and 160): Nos. 23, 34, 51, 52,
95, 97, 98, 101, 102, 105, 115 and 116. The inspector reviewed the
Weld Data Sheets for penetrations 23, 51, 52, 95, 97, 98, 101, 102,
105, 115 and 116 noting the requirements for such items as fitup,
nondsetructive testing (NDE) and weld procedure.
b.
(Closed) Item 50-339/78-36:05 Service Water Reservoir Spray System
Pipe Break, Unit 2.
The inspector reviewed the VEPC0 final report
dated February 9, 1979, serial number 720 B, the interim reports dated
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December 15, 1978 and January 10, 1979, and the corrective action as
reported in Nonconformity and Disposition Reports (NED) Nos. 3610 and
3730 and E&DCR's P-2549, P-2583 and P-5217. These reports document
the repairs, modificatione and installation of the service water spray
and header piping and supports as described in the final report dated
February 9,1979.
The inspector reviewed the QC inspection reports and observed in the
storage areas typical specimens of damaged pipe, repaired pipe and new
pipe.
c.
(Closed) Items 50-339/79-21-05, Reactor Coolant Pump Flow Splitter
Plates, Unit 2.
The inspector reviewed the VEPCO final report dated
May 4,1979, serial number 191 B, and the interim reports dated March 27,
1979 and April 20, 1979 relative to the cracks found in the subject
splitter plates for the pumps in loops A and C of Unit 2.
The corrective
action was to remove the splitter plates from all three loops of
Unit 2.
KRR is reviewing the hydraulic system changes and the causes
of the cracks. Westinghouse has determined that the effect of removing
the plates is negligible upon pump performance and tbst the resultant
flow provides a margin of flow that is conservative and acceptable.The
resident inspector visually inspected the inside surfaces of the
piping after the splitter plates were removed. This item was closed
for Unit 1 in IE Report 50-33/79-20.
The inspectot reviewed the documentation in NSD 3731 of the repair
work, the NDE testing, the content of the materials and the QC surveil-
lance of the repair work. There has been no reduction in the thickness
of the pipe wall.
d.
(Closed) Item 50-339/79-21-06, Motor Control Center (MCC) Starter for
Motor Operator Valve (MOV) RS-201B, Unit 2.
The inspector reviewed
the VEPC0 final report dated April 3, 1979, serial number 209, and the
corrective action as reported in N&S 3/28 for completed work on the
subject starter in cabinet 2-EP-MC-20. The inspector observed similiar
work in cabinet 2-EP-MC-11 and discussed the potential generic implica-
tions with appropriat
SW staff and the K-M project engineer for the
subject reversing r
starter supplied by K-M. There are an estimated
1300 to 1500 of thea_ starters used in Units 1 and 2 (aproximately 300
in class IE applications). Discussions with senior S & W staf f and the
K-M project engineer confirm the low failure rate reported by VEPC0; i.e. ,
three class IE f ailures and less that three failures for a;l nonclass IE
reversing starters supplied by K-M.
The K-M project engineer has visited the site for each f ailure. The
starter is a catalog item, hence it is not under Part 21 reporting
requirements. The defects were sustained during a construction checkout
procedure and corrected prior to being released to the Operati_as. Groups.
VEPCO concludes that this f ailure does not represent a generic defect with
the equipment.
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e.
(Closed) It m 50-339/79-28-02, Flux Thimble Tubing, Unit 2.
The
inspector reviewed the VEPC0 final report dated April 9,1979, serial
number 235, the corrective action to replace all the flux thimble
tubing for incore instrumentation as reported in NCD 3745, and the QC
inspection report of the work performed in accordance with directions
provided by Westinghouse.
f.
(Reopen and Clos d) Item 50-404/405/78-07-06, Recirculation Spray
Cooler Vent Problem (Units 3 & 4). The inspector reviewed the S&W to
VEPC0 letter dated May 10, 1979, which transmitted their review and
approval for Joseph Oat Corporation report " Water Hanner Analysis of
the Recirculation Coolers, Revision 2"
and related correspondence
concerning the analysis. The revision reviews a more vigorous analysis
of the effect of flow transients in the recirculation coolers that
corrects certain errors and inadequacies noted in the original analysis.
During the various reviews of the water hammer analysis, S&W independently
calculated the tube deflection.
S&W concurs with the Joseph Oat
Corporation conclusion that the existing cooler design is satisfactory
and capable of withstanding the startup hydraulic transient.
No noncompliances were identified.
6.
It Bulletins (IEB)
(Closed) IEB 78-12 Atypical Weld Material in Reactor Pressure Vessel
a.
Welds, Units 3 and 4.
The inspector has reviewed the VEPC0 response
to Region II dated May 17, 1979, serial number 322, which provides all
the required responses to IEB's 78-12,78-12A and 78-12B.
B&W the
manufacturer of the North Anna 3 and 4 vessels, has prepared a generic
report to the NRC dated March,1979 responding to IEB's 78-12 and
78-12A, indicating no atypical weld material in the Unit 3 and 4
vessels. VEPC0 has reviewed the material records for the vessels and
has verified that the B&W report covers all applicable welding wire
employed for the Unit 3 and 4 vessels and concurs with the B&W negative
conclusion,
b.
(Open) IEB 79-03 Longitudinal Weld Defects in ASME SA-312 Type 304
Stainless Steel Pipe Spools Manfactured by Youngstown Welding and
Engineering Company, Units 2, 3, and 4.
VEPCO's letter dated May 10,
1979, inf o rms Region II of their extensive record review and their
need for an additional 30 days minimum to reply.
(Closed) IEB 79-04 Incorrect Weights for Swing Check Valves Manufactured
c.
by Velan Engineering Corporation, Unitt 3 and 4.
VEPCO's letter dated
May 24, 1979 informs Region Ti that no Velan check valves have been
purchased for Units 3 and 4.
d.
(0 pen) IEB 79-07 Seismic Stress Analysis of Safety Related Piping,
Units 3 and 4.
VEPCO's letter to Region II dated May 24, 1979 inf o rms
Region II that no cor.puter codes were employed which used any of the
methods described in item 1 of IEB 79-07.
Inforuation submitted in
response to other items in the 16B has not been evaluated.
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No items of ncncompliance were identified.
7.
Independent Inspection
Site QC Organization and Program, Units 3 and 4.
The inspector reviewed
a.
the VEPCO Construction Quality Control Manual (CQCM) Appendix A dated
May 22, 1979, which provides (attachment 1) an organization chart with
titles that have been prepared and conceptually approved by VEPCO
listing of responsibilities of the
management and (attachment 2) a
interim organization. For the interim period before full construction
resumes on Units 3 and 4, the organization is to fulfill the assigned
responsibilities.
The responsibilities include an itec related to a QA audit program of
construction activities by staff positions labeled QA on attachment 1
of Appendix A, QC on attachment 7.1 of CQCM 1.1, and both QA and QC on
attachment 2 of Appendix A. CQCM Procedure 1.1 provides for VEPC0 site
staf f to perform site OC work on Units 3 and 4 with VEPC0 Richmon? staf f
to perform the QA function. A consistant clarification of responsibi-
lities for QA and QC work will be unresolved item 50-404/405/79-05-01
" Auditing of Construction Activities".
The inspector revicwed the CQCM relative to the evaluation of 10 CFR 50.55 (e) items as required by the VEPC0 QA Manual, Section 5.13. Addi-
tional Procedures in the CQCM need to be provided to assure evaluation
of 10 CFR 50.55(e) items by the first level of management. This will be
designated as unresolved item 50-404/405/79-05-02, " Resident QC Engineer-
ing Evaluation of 10 CFR 50.55(e) Items".
b.
Containment Structural Concrete, Unit 3
The inspector observed the placement of part of the first lift for the
containment wall of Unit 3 and reviewed the Specification, NAS-30120,
for placing the concrete and CQC Procedure 10.2, Concrete Quality Control.
This activity is covered in Report No. 50-404/79-6.
No items of noncompliance were identified.
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