IR 05000400/1979015
| ML18017A661 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/05/1979 |
| From: | Bradley R, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18017A659 | List: |
| References | |
| 50-400-79-15, 50-401-79-15, 50-402-79-14, 50-403-79-14, NUDOCS 7910180081 | |
| Download: ML18017A661 (8) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-400/79-15, 50-401/79-15, 50-402/79-14, and 50-403/79-14 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name:
Shearon Harris Nuclear Power Plant Docket Nos. 50-400, 50-401, 50-402, and 50-403 License Nos.
CPPR-158, CPPR-159, CPPR-160, and CPPR-161 Inspection at Shearon Harris Site near Raleigh, North Carolina Inspector:
R.
. Bradley ate Signed Approved by:
. Brya
, Section Chief, RCES Branch Date Signed SUMNARY Inspection on August 13-16, 1979 Areas Inspected This routine, announced inspection involved 27 inspector-hours onsite in the areas of construction status; licensee identified items; IE bulletins; organiza-tional and functional alignment; Cadwelding; welding repair; and observation of construction activities in progress in the powerblock, dams, and emergency service water intake channel.
Results Of the areas inspected, no items of noncompliance or deviations were identifie DETAILS 1.
Persons Contacted Licensee Employees
~M.-A.
"P.
W.
-W. B.
"S. D.
-N. J.
nT.
"R. M.
-A. M.
"G. L.
McDuffie, Senior Vice President, Engineering and Construction Howe, Vice President, Technical Services Kincaid, Vice President, Power Plant Engineering Smith, Vice President, Power Plant Construction Chiangi, Manager, Engineering and Construction gA
'yllie, Senior Construction Manager Parsons, Site Manager Iucas, Senior Resident Engineer Forehand, Principal gA Specialist Other licensee employees contacted included one geologist, two civil engineers, one mechanical engineer, two gA specialists, and several construction craftsmen and area superintendents.
Other Organizations
- W. D. Goodman, Project Manager, Daniel Construction Company
+Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on August 16, 1979 with those persons indicated in Paragraph 1 above.
The inspector also summar-ized the findings of inspector J. J.
I,enahan which were the result of a civil inspection held August 13-15, 1979.
3.
Licensee Action on Previous Inspection Findings h
Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Construction Status The inspector observed construction activities underway at the main and auxiliary dams, emergency service water (ESW) intake channel, containment dome erection area, Unit 1 containment, turbine generator
~ off-loading area, and the structural fabrication shop.
Examinations were made of data 'concerning rock fillfor the main dam and previously
placed fillin the ESW intake channel, handling activities during off-loading of the Unit 1 turbine generator stator, Cadwelding in the Unit 1 containment secondary shield wall, and weld repairs on the reactor coolant pump supports.
Hake, Incorporated will be responsible for raising and setting the 953,000 pound generator stator for Unit No.
1.
Chicago Bridge and
'Iron is continuing to work on the dome plate preassembly and on the actual dome erection.
Rigging International is scheduled to begin erecting the derrick crane on October 15, 1979 in preparation for setting the Unit No.
1 nuclear steam supply system components and containment dome.
Concrete placed to date totals 265,000 cubic yards.
Reinforcing steel quantities total 34,000 tons.
The combined work force now totals some 3,440 persons.
b.
Nuclear Reactor Regulation (NRR) Examination of Main Dam and ESW Intake Channel On August 13-14, 1979, the inspector accompanied O.
Thompson of NRR, and NRR consultant G. Baer of the Corps of Engineers du.ring"an exami-nation and data review of safety related fillfor the main dam and ESW intake channel.
Information on this review and the findings of the subsequent civil inspection can be found in inspection report number 50-400,401/79-16 and 50-402,403/79-15.
C.
Containment Cadwelding On August 14, 1979, the inspector observed Cadwelding activities underway in the secondary shield wall within Unit 1 containment.
Discussions were held with the area superintendent, gA inspector, gA specialist and craft personnel.
Four horizontal splices were moni-tored during bar length cutting, cleaning, preheating, sleeve positioning and preheating.
Cadwelding was accomplished using F-105 filler material and activities were performed in accordance with procedure CgC-15, Cadweld Control. The splice sleeves were properly identified with the splicer's symbol (CO-077)
and his qualifications were verified by examination of the licensee's records.
d.
Structural Meld Repairs Meld repair activities in progress on a reactor coolant pump support in the structural fabrication shay were monitored by the inspector bn August 15, 1979.
Four supports w'erk rejected during receiving inspec-tion for failing to meet the welding requirements of AWS Dl.l, namely, undercut exceeding 1/32", lack of fusion, and excessive porosity.
In addition, the coating of inorganic zinc had been improperly applied.
The inspector examined the deficient welds/ coating, reviewed the deficiency and disposition report (DDR-232), field inspection reports, job order number 69, fabrication request for repair, associated vendor correspondence, applicable drawing (1364-11976R1),
and corrective action report.
Discussions were held with the receiving gA
specialist, welding QA specialist and applicable QA inspector, and the mechanical unit engineer.
The RII inspector confirmed that the licen-see had properly identified, documented, and reviewed the subject deficiency.
Corrective action was being taken in accordance with established procedures and the deficiency did not constitute an item reportable under
CFR 50.55(e).
The inspector has no further questions.
Organizational and Functional Alignment of Site Inspection Personnel The inspector reviewed and discussed the organizational and functional alignment for accomplishing and monitoring tests and inspections of activities affecting quality at the site.
As previously outlined in inspection report 50-400,401,402,403/77-3, CPSL is responsible for managing construction activities performed by Daniel Construction Company (DCC) and verifying (auditing, inspecting, and testing) that these construction activities are being accomplished in accordance with instructions, procedures, specifications, and drawings.
The CPSL Construction Inspection Unit reports directly to the senior resident engineer and is an autonomous organization which is separate from the CPRL construction engineering unit disciplines.
This unit is responsible for performing specific electrical, mechanical, and civil QC inspections and tests to verify that DCC performance is in conform-ance with the documented instructions, procedures, specifications and drawings for accomplishing the activity.
The GPSS'ite QA Unit moni" tors DCC and the Construction Inspection Unit to assure proper imple-mentation of the site QA, work, and technical procedures.
The site QA Unit reports offsite to the Engineering and Construction QA Manager and is independent of site construction management.
Other QC inspections and tests such as receiving acceptance, welding, NDE, and civil activities conducted by the Concrete Materials Labora-tory, are performed by the site QA Unit.
Their performance is audited by the Corporate Nuclear Safety and QA Audit Section which reports to upper management through channels that are independent of power plant construction responsibilities.
Corporate audit personnel have no responsibilities for quality achievement, other than auditing the Engineering and Construction QA Program which is being implemented by CPSL and its contractor '
Personnel performing inspection, test, and auditing/monitoring activities are being trained and qualified in accordance with the following established program procedures:
1.
Construction Inspection Personnel a
~
TP-14, "Training and Qualification of Civil Construction Inspection Personnel" b.
TP-26, "Training and Qualification of Mechanical Construc-tion Inspection Personnel" C.
TP-27, "Training and Qualification of Electrical Construc-tion 'Inspection Personnel" 2.
Site QA Inspection Personnel a.
CQA-l, "Personnel Training and Qualitification" b.
SHNPP Nondestructive Examination Manual 3.
Corporate Nuclear Safety and Audit Personnel a.
QAAI-2, "Instruction for Training and Qualification of QA Program Audit Personnel" Based on the above evaluation, the inspector has concluded that:
1.
Sufficient independence from cost and scheduling has been established for the CPM Construction Inspection organization to avoid compromise of quality.
2.
Inspections and tests are being performed by personnel other than those who performed the construction activity being inspected.
3.
Auditing/monitoring functions are being performed by personnel not having direct responsibilities in the areas being audited.
4.
The implemented QA program has provided for training and qualification of personnel performing inspection,- test, and auditing activities as necessary to assure that suitable: proficiency is achieved and maintained.
Within the above areas of inspection, no items of noncompliance or deviations were identifie.
Licensee Identified Items (10 CFR 50.55(e))
Prior to this inspection, the licensee had identified several items which were reportable under
CFR 50.55(e).
The items and their status are as follows:
a
~
(Open) Item (400,401/79-14-01 and 402,403/79-13-01),
Improper welds on engineered embedment plates.
Region II was notified by the licensee on August 6, 1979 that this potentially reportable item had been determined to be reportable under
CFR 50.55(e).
Based on discus-sions with responsible site personnel an'd a review of the deficiency
'nd disposition report (DDR-269), the inspector concurs in this determination.
This evaluation is continuing and will remain open pending receipt, review, and evaluation of the licensee's report which is scheduled for submittal by September 5,
1979.
b.
C.
(Closed)
Item (400/79-12-02),
Containment penetration collars not heat treated.
The licensee's final report on this 55(e) deficiency was received on August 6, 1979.
The inspector reviewed and evaluated the report and held discussions with site gA personnel.
All affected penetrations have been reworked by the vendor.
The inspector has no further questions.
(Closed) Potential CDR (400,401/79-12-01 and 402,403/79-11-01),
Indications in service water pipe.
This item was previously closed out in inspection report 400,401/79-12 and 402,403/79-11.
Through an administrative error, it was incorrectly stated that the service water pipe had already been installed when the linear indications were found.
The piping was actually located adjacent to the structural fabrication shop when the licensee detected the indications.
This correction confirms a discussion held with the licensee on August 1, 1979.
7.
Inspection and Enforcement Bulletin Status a ~
b.
(Closed) 79-BU-ll:
Faulty Overcurrent Trip Device in Circuit Breakers for Engineered Safety Systems.
The licensee's response of July 27, 1979 reported that there are no Westinghouse DB-50 and DB-75 circuit breakers planned for use in safety related systems at the Harris site.
(Open)
79-BU-14:
Seismic Analyses for As-Built Safety-Related Piping Systems.
The licensee has stated: in his response dated August 1, 1977, that the items in this bulletin cannot be addressed at the current time due to the fact'hat as of August 1, 1979, there are no completed safety-related piping systems installed.
Therefore, there are no as-built drawings that a stress analysis impact can be compared to.
As a part of the licensee's gA and startup programs, as-built configurations will be checked against the design used in the seismic analysis, and any necessary changes will be made.
This item will remain open pending completion of a review by IE Headquarters.