IR 05000400/1979014
| ML18003A660 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/10/1979 |
| From: | Bradley R, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18003A658 | List: |
| References | |
| 50-400-79-14, 50-401-79-14, 50-402-79-13, 50-403-79-13, NUDOCS 7909210183 | |
| Download: ML18003A660 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-400/79-14, 50-401/79-14, 50-402/79-13, and 50-403/79-13 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 Shea n Harris Site near Raleigh, North Carolina Inspector:
R. D.
B a ley D te igned Approved by:
J
. Bryan Section Chief, RCES Branch at igned SUMMARY Inspection on July 23-26, 1979 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours onsite in the areas of construction progress; licensee action on previous inspection findings; review of licensee gA manual proce-dures; licensee identified items; IE bulletins;.storage; and a
walk-through inspection of the power block, main and auxiliary dams, NDE laboratory, industrial radiography building, and large component storage yard.
Results Of the areas inspected, no items of noncompliance or deviations were identifie DETAILS 1.
Persons Contacted Licensee Employees
+S. D. Smith, Vice President, Construction Department
"R. M. Parsons, Site Manager A. M. Lucas, Senior Resident Engineer Q. L. Forehand, Principal QA Specialist W. Mercer, gA Welding Inspector D. Whitehead, Senior gA Material Control Specialist Other licensee employees contacted included one geologist, two senior gA specialists, one licensing engineer, three engineering supervisors, and two office personnel.
Other Organizations-W. D. Goodman, Project Manager, Daniel Construction Company J. Given, Lumbermen's Mutual Insurance Company, Authorized Nuclear Inspector-Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on July 26, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 400/79-10-01, Inoperative concrete truck revolution counter.
The inspector held discussions with the senior resident engineer and observed the operation of a new roller-plunger actuated electric counter.
All new counters had been received and installed prior to the conclusion of this inspection.
4.
Unresolved Items Unresolved items were not identified during this inspectio.
Independent Inspection a.
Construction Progress The inspector conducted a walk-through inspection of the power block, main and auxiliary dams, large component class D
storage area, NDE laboratory, and the industrial radiography building.
Observations were made of the initiation of a concrete placement for two columns in the Unit 1 reactor auxiliary building, installation of re-bar around the Unit
containment liner, three service water line welds for Units 3 and 4, and maintenance of dry gas blankets for safety related heat exchangers.
The Board of Directors has announced a one year delay in construction of Units 3 and 4 based on revised load forecasts.
Chicago Bridge and Iron has completed its dome erection founda-tion at the site and the first section has been erected.
When completed, the dome will be maneuvered near the powerblock on a device using a cushion of air and then lifted by crane into place, atop the containment structure.
The first steam generator undergoing an auxiliary feedwater nozzle installation is nearing completion.
Preliminary x-ray testing will be con-ducted prior to stress relieving.
b.
Heat Exchanger Storage The inspector reviewed the system established by the licensee to control Level D storage of mechanical equipment to verify that protective environments had been specified and provided as required by Criterion XIII of Appendix B to 10 CFR 50.
The following procedures are applicable to this area:
AP-XIII-05 R8, Material Storage AP-XIII-07 R12, In-storage Inspections and Maintenance WP-106 R3, Maintenance/Protection of Mechanical Equipment SHNPP R8, Material and Equipment Storage Requirements SHNPP R9, Material Maintenance Requirements During Storage The inspector reviewed the above procedures and held discussions with the senior gA material control specialist and members of the mechanical engineering unit.
Two spent fuel pool heat exchangers installed in the fuel handling building, and
various safety related heat exchangers awaiting installation in storage yard locations D-10 and E-10 were selected for inspection.
An examination of the components on July 24, 1979
revealed that dry gas blankets had been established as required, adequate drainage (D-10 and E-10 areas)
had been provided, and appropriate maintenance logs had been established.
However, three of the 25 exchangers examined in the storage yard were noted as having zero gauge pressure on the shell-side gauge.
A review of in-storage inspection reports for theseWree components revealed that, in accordance with established procedures, the gauges were verified as having in excess of
psig on July 13 and 20, 1979; therefore, the pressure was lost sometime during the interim period.
The execution of the next weekly inspection on July 27, 1979 should have identified this nonconformance for correction.
c ~
Service Water Line Welding On July 23, 1979, the inspector observed the construction welding activities underway on the 30" service water line for Units 3 and 4.
Field welds 188 and 206 for Unit 3 and field weld 199 for Unit 4 were visually examined by the inspector.
Discussions were held with the QA welding inspector and one of the three pipe welders (B10) involved.
Shielded metal arc butt welding utilizing a backing ring was performed to ASME Section III, code class 3, using E 7018 filler metal per Weld Procedure Specification P-l-l-A-l, revision 2.
No post weld heat treatment is required by this specification.
The inspector reviewed the applicable drawings, weld specification, weld data reports, NDE requests and reports, and the performance qualification test records for the welders involved.
Within the above areas of inspection, no items of noncompliance or deviation were noted.
6.
Welding (Steel Structures/Supports and Piping - Other than reactor coolant loop) - Review of QA Implementing Procedures (Units 1 and 2)
The inspector reviewed the documents listed below and held discussions with responsible CPRL personnel concerning the associated QA program work in the area of welding.
The examination performed addressed safety related steel structures/supports and piping (reactor coolant loop excepted) for Units 1 and 2.
The following Construction QA Procedures (CQA), Construction QC Procedures (CQC), Quality Assurance Audit Procedure (QAAP), Quality Assurance Audit Instruction {QAAI), Construction Administrative Procedure (AP), Construction Technical Procedures (TP), COL Corporate QA Manual, SHNPP ASME QA Manual, and EBASCO Specifications, were reviewed as typical of the applicable documents:
CQA-l, Personnel Training and Qualification
CQA-2, QA Document Control CQA-4, QA Records CQA-5, Document Reviews CQC-l, Tool and Measuring Device Control CQC-2, Noncompliance Control CQC-4, Procurement Control CQC-6, Receiving Inspection CQC-8, Storage Control CQC-19, Weld Control CQC-20, Post-Veld Heat Treatment Control QAAP-1, Procedure for Corporate Audits QAAI-l, Corporate Procedures for QA Audit Documents AP-lV-03, Preparation, Approval, and Control of Procedures TP-04, Calibration of Controlled Tools TP-17, Construction Inspection Noncompliance Control TP-32, Structural Steel Inspection CPSL Corporate QA Manual SHNPP ASME QA Manual CAR-SH-M-30, General Power Piping, Nuclear Safety Class 1,
2 and
No items of noncompliance or deviations were identified.
7.
Licensee Identified Items Prior to this inspection, the licensee identified the following items under
CFR 50.55(e):
a.
(Closed)
Item (400, 401/79-10-02 and 402, 403/79-09-02),
Defective class 3 component cooling heat exchangers.
Region II was notified by the licensee on July 13, 1979 that this potentially reportable condition had been evaluated and determined to be nonreportable.
The inspector talked with members of the licensee's QA section and mechanical engineering unit, and the site authorized nuclear code inspector, and reviewed a copy of
Westinghouse letter CgL-5450 on the results of their investiga-tion of this deficiency.
The inspector concurred in the licensee's justification for nonreportability.
The eight affected heat exchangers were being purged for reconnection to a nitrogen source during this inspection and will remain in this state until repair/rework is commenced.
b.
(Open) Item (400/79-12-02),
Containment penetration collars not heat treated.
As recorded in inspection report 400,401/79-12, this item has been determined to be reportable under
CFR 50.55(e).
The inspector reviewed the applicable deficiency and disposition report (DDR-259), corrective action report, conditional release request and associated correspondence'his item will remain open pending receipt, review, and evalua-tion of the licensee's report.
c ~
(Open) Item (400, 401/79-14-01 and 402, 403/79-13-01),
Improper welds on engineered embedment plates.
The licensee reported the subject potentially reportable deficiency to Region II on July 6, 1979. It was noted by site personnel that of four vendors supplying engineered embedment plates, one used fillet welds rather than the required 100$ penetration welds to attach threaded bar stock to the plates.
The licensee is in process of identifying the quantity and location of the plates received from this particular vendor.
In those instances where plates are found to be already installed, their location will be identified on drawings and individually evaluated relative to known loads by the architect-engineer Ebasco.
This item will remain open pending completion of COL's evalua-tion.
8.
Inspection and Enforcement Bulletins, Circulars, and Information Notices The inspector contacted the Nuclear Licensing Unit in Raleigh to coordinate the bulletins, circulars, and information notices issued by Region II over the past several months. It was determined that the applicable documents had been received, appropriate action was being taken, and a proper response date had beeh established, as required.
a.
(Open)
IEB 78"12B, "Atypical Weld Material in Reactor Pressure Vessel Welds" The licensee's response dated May 29, 1979 for vessels 1 and 2,
and a supplemental response dated July 9, 1979 for vessels 3 and 4, have been received and reviewed.
CPS'as determined that, based on their review of the fabricators'eneric reports of weld materials used, they are satisfied that the reports adequately represent data for the reactor pressure vessels for Harris Units 1, 2, 3 and 4, with editorial changes as noted.
This item will remain open pending completion of IE Headquarters evaluatio b.
(Open)
IEB 79-02Rl, "Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts" The licensee's response dated July 6, 1979 has been received and reviewed by RII. CPSL stated that they do not plan to use concrete expansion anchor bolts for the specified application.
In case a need is'ater identified, a selection criteria has been outlined.
This item will remain open pending review by IE Headquarters.