ML19256F079
| ML19256F079 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/26/1979 |
| From: | Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256F075 | List: |
| References | |
| 50-412-79-06, 50-412-79-6, NUDOCS 7911210307 | |
| Download: ML19256F079 (8) | |
See also: IR 05000412/1979006
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
Region I
Report No. 50-412/79-06
Docket No. 50-412
License No. CPPR-105
Priority
--
Category
A
Licensee:
Duquesne Licht Comoany
435 Sixth Avenue
Pittsburah, Pennsylvania
15219
Facility Name: Beaver Valley Power Station. Unit 2
Inspection at: Pittsburgh and Shippingport, Pennsylvania
Inspection cond ted:
u st 27-30, 1979
Gt/b4/
7
Inspectors:
f,u ,
/ date signed
L. Narrow, Reactor Inspector
date signed
date sicned
f/16 78
Approved by:
N,M //l4
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u
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sfgned
'
R. W. McGaughy, Mik Projects Section,
RC&ES Branch
Inscection Summary:
Inspection on August 27-30, 1979 (Recort No. 50-412/79-06)
Areas Inspected:
Routine,
announced inspection by a regional based inspector
-
to7eview compliance with the ASME certification system; compliance with 10 CFR 21; the QC program for erection of safety related steel structures; and, the
status of Bulletins, Circulars and other outstanding items.
The inspection
involved 8 inspector-hours in the licensee's office and 18 inspector-hours on
site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
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Region I Form 12
(Rev. April 77)
7911210 3 0]
.
.
D_E_ TAILS
E
1.
Persons Contacted
Duquesne Light Company (DLC)
- H. N. Crooks, Supervisor, Adminie'rative Services
- R. Coupland, Director of Qual cy Control
- D. W. Denning, Assistant Director of Quality Control
E. J. Huesmann, Administrative Coordinator (Pittsburgh)
- E. F. Kurtz, Senior QA Engineer
D. Rohm, Quality Control Engineer
- W. H. Sikorski, Quality Assurance Supervisor
E. Staples, QC Engineer
- R. J. Swiderski, Superintendent of Construction
H. Van Wassen, Project Manager (Pittsburgh)
- R. Washabaugh, Manager, Quality Assurance Department
R. L. Williamson, Quality Control Inspector
Stone and Webster (S&W)
S. T. Adams, Superintendent of Construction Services
- C. R. Bishop, Superintendent of Construction
P. N. Bodine, Supervisor of Document Systems
S. M. Dew, Head of SE0
A. C. McIntyre, Site Engineering Office
V. W. Pardo, Resident Engineer
C. R. Paul, Purchasing Agent
R. J. Wood, ASME Program Administrator
Schneider, Incorporated
J. Zielinski, Field Engineer
The inspectcr also interviewed other licensee and contractor personnel
during the ir e,pection.
- denotes those present at the exit interview.
2.
Plant Tour
The inspector observed work activities in progress, completed work, and
construction status in several areas.
Work items were examined for obvious
defects and for noncompliance with regulatory requirements and licensee
conmitments. Specific activities observed by the inspector included rein-
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forcing steel installation for the primary shield wall, weld rod storage
issue and control at Schneider, Incorporated Distribution Center No. 4 in
the auxiliary building, and installation of service water lines 258 and
259.
No items of noncompliance were identified.
3.
Compliance witi.10 CFR 21
The inspector examined DLC and S&W procedures for compliance with the
requirements of 10 CFR 21 and audited implementation of these procedures.
The following procedures were examined:
DLC Quality Assurance Memorandum DLC QA-2150, dated December 16, 1977,
-
" Requirements of 10 CFR 21."
DLC Engineering Management Procedure EMP8.1, Revision 3, dated February
-
14,1979, " Report of Sign'ficant Deficiencies and Deviations - De-
sign / Construction Phase."
S&W Construction Management Manual CMM No. 410, Revision 0, dated June
-
29, 1979, " Reporting of Significant Problems."
S&W Field Purchasing Manual Section V, " Purchase Orders and Memos of
-
Charge," Attachment V.H.
The inspector discussed implementation of these procedures with representa-
tives of the licensee and S&W, particularly with respect to inclusion of
these requirements in site purchase orders, evaluation of deviations,
notification of a Director / Responsible Officer (D/R0) and notification to
NRC.
The inspector observed that the required documents had been posted in
several locations at the DLC office in Pittsburgh, at the DLC QA/QC offices
at the site, and at the S&W offices at the site.
The inspector noted that DLC QA-2150 and EMP 8.1 establish procedures which
appear to be inconsistent with the requirements of 10 CFR 21 in two respects.
a.
Both of these documents provide for evaluation of deficiencies and for
submittal of a written report of a reportable deviation within 30 days
after initial NRC notification.
This does not meet the 10 CFR 21
requirement (21.21(b)(2)) that a written report be submitted within 5
days after the information is obtained.
b.
These documents also do not require that the D/R0 be notified of a
reportable deviation until submittal of the written report which may
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be as much as 30 days after the information is obtained.
This does
not appear to be consistent with 10 CFR 21. Although 21.21(b)(4) does
state that the D/R0 may authorize an individual to provide the required
notification, 21.21(a) requires that the D/R0 be informed of the
deviation.
In addition, the delay in informing the D/R0 would appear
to affect imposition of a penalty since 21.61 states that the D/R0 is
subject to a civil penalty if he "--knowingly and consciously fails to
provide such notice- ."
This item is unresolved pending clarification of the above inconsistencies
(.412/79-06-01).
4.
Compliance with ASME Certification Requirements
The inspector identified the effective dates of ASME codes applicable to
this project and audited the responsibilities and activities of the certi-
ficate holders.
Authorizations in effect on site included:
Certificate No. N-2026 to DLC. Authorization to complete Form N-3 for
-
Beaver Valley Power Station, Unit 2; effective dated March 8,1978 to
March 8, 1981.
Certificate No. N-1513-2 to S&W.
Authorization to use "N" symbol for
-
construction of Beaver Valley Unit 2 for which fabrication and instal-
lation is subcontracted to certificate holders; effective dated June
18, 1979 to June 18, 1982.
Certificate No. 1824-1 to Schneider, Incorporated.
At thorization to
-
use "NA" symbol for field installation of components, appurtenances,
piping subassemblies, and component supports at Beaver Valley Unit 2;
effective dated August 12, 1977 to August 12, 1980.
Certificate No. 1825-1 to Schneider, Incorporated.
Authorization to
-
use "NPT" symbol for field fabrication of component supports and
piping subassemblies at Beaver Valley Unit 2; effective dated August
12, 1977 to August 12, 1980.
Certificate No. N-1472-7 to Richmond Engineering Company, Incorporated.
-
Authorization to use "N" symbol for field construction of Class 3
vessels and tanks at Beaver Valley Unit 2; effective dates October 4,
1978 to October 4,1981.
Richmond Engineering Company was not working
on site at this time, but had installed some tanks on site and would
return for construction of some additional tanks.
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.
The inspector was informed that Pittsburgh-Des Moines Steel Company would
be performing ASME III work on site in the future but had not been surveyed
for authorization as yet.
No items of noncompliance were identified.
5.
pocumentation - Boric Acid Tank No. 2CHS-TK-21B
The inspector audited documentation listed below concerning Tank No. 2CHS-
TK-218 for conformance to the requirements of the PSAR and S&W Specification
2BVS-33, " Specification fo* Field Fabricated Tanks."
Form N-1, " Manufacturers Data Report for Nuclear Vessels."
-
A random selection of Material Test Reports.
-
Cleaning Certification.
-
Radiographic Interpretat an Reports.
-
Certification of Delta Ferrite Examination.
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Certification of PT Examination.
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Certification of Vacuum Box and Hydrostatic Tests.
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QC and NDE Qualification Records.
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Field Erection Operational Work Sheet.
-
The inspector also examined N&D No. 0766 for deficiencies in analysis of
water for test purposes. This was resolved on the basis of retest of a
water sample and engineering review of identified deficiencies.
No items of noncompliance were identified.
6.
Licensee Action on NRC Bulletins and Circulars
The inspector reviewed records concerning the licensee's action on NRC
issued Bulletins and Circulars and discussed these actions and records with
licensee personnel responsible for processing Bulletins and Circulars.
The following Bulleons were closed based on information from S&W and the
NSSS that the equipment in question had not been used and would not be used
in this plant:
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Bulletin No.
Subject
78-06
Defective Cutler-Hamer, Type M Relays with DC Coils
78-10
Bergen-Paterson Hydraulic Shock Suppressor Accumulator
Spring Coils
79-03
Longitudinal Weld Defects in ASME SA-312 Type 304
Stainless Steel Pipe Spools Manufactured by Youngstown
Welding and Engineering Company
79-04
Incorrect Weights for Swing Check Valves Manufactured
by Velan Engineering Corporation
79-11
Faculity Overcurrent Trip Device in Circuit Breakers
for Engineered Safety Systems
The following Circulars a e closed because they either do not apply or
because records show that corrective action hss been taken to prevent
conditions described in Circular.
Circular No.
Description
76-03
Radiation Exposure in Reactor Cavities
77-01
Malfunctions of Limitorque Valve Operators77-02A
Potential Heavy Spring Flooding
77-03
Fire Inside a Motor Control Center
77-05
Liquid Entrapment in Valve Bonnets
77-06
Effects of Hydraulic Fluid on Electrical Cable
77-13
Reactor Safety Signals Negated During Testing
77-15
Degradation of Fuel 0.1 Flow to the Emergency Diesel
Generator
78-02
Proper Lubricating Oil for Terry Turbines
78-03
Packaging Greater Than Type A Ouantities of Low
Specific Activity Radioactive Material for Transport
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78-04
Installation Errors That Could Prevent Closing of
Fire Doors
78-05
Inadvertent Safety Injection During Cooldown
78-06
Potential Common Mode Flooding of ECCS Equipment
Rooms at BWR Facilities
78-09
Arcing of General Electric Company NEMA Size 2 Con-
tractors
78-13
Inoperability of Multiple Service Water Pumps
78-15
Tilting Disk Check Valves Fail to Close with Gravity
in Vertical Position
78-16
Limitorque Valve Actuators
78-19
Manual Override (Bypass) of Safety Systems Actuation
Signals
79-04
Loose Locking Nut on Limitorque Valve Operators
79-11
Design / Construction Interface Problem
79-12
Potential Diesel Generator Turbocharger Problem
The following Circulars remain unresolved for the reasons shown:
Circular No. 77-11, Leakage of Containment Isolation Valves with
-
Resilient Seats, pending determination whether valve types identified
in vendor letter are on site and if so whether storage recommendations
are being followed (50-412/77-Cl-ll).
Circular ;1o. 79-02, Failure of 120 Volt Vital AC Power Supplies,
-
pending response from Station Superintendent (50-412/79-C1-02).
7.
Problems Identified at Other Sites
The inspector informed the licensee representatives of problems which had
teen identified at other sites with the following equipment:
Tanks Fabricated by Industrial Piping Supply Company
-
Power Operated Relief Valves by Control Components, Incorporated
-
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The inspector was informed that review by the licensee and S&W showed that
equipment of the type described had not been obtained from these companies
and that the companies were not on their approved bidders list.
The inspector had no further questions concerning this item.
8.
Licensee Action on Previous Inspection Findings
(0 pen) Unresolved Item (78-01-01):
Licensee action on Circulars.
The
inspector examined " Project Team Internal Instruction," PTG-4, dated November
16, 1978, which provides for distribution of Bulletins and Circulars and
action assignment by the Project Manager.
The inspector also discussed
control and followup methods with the licensee representative and examined
the log which was maintained and which included the Bulletins and Circulars.
The inspector had no further questions concerning control of Circulars.
However, this item remains open pending completion of action on Circulars
77-01 and 77-14.
(Closed) Unresolved Item (78-BC-01):
1/2-inch Nelson Studs from Acme Steel
Company.
Site QC has been informed by procurement that Acme Steel Company
is not a supplier and no Acme Steel Company material had been suppliea on
the site.
9.
Exit Interview
The inspector met with licensee and contractor representatives (denoted in
Paragraph 1) at the conclusion of the inspection on August 30, 1979.
The
inspector summarized the scope and findings of the inspection as described
in this report.
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