IR 05000400/1979006
| ML18017A525 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/19/1979 |
| From: | Bradley R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18017A521 | List: |
| References | |
| 50-400-79-06, 50-400-79-6, 50-401-79-06, 50-401-79-6, 50-402-79-05, 50-402-79-5, 50-403-79-05, 50-403-79-5, NUDOCS 7905250020 | |
| Download: ML18017A525 (7) | |
Text
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VNITEDSTATES NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA.GEORGIA 30303 Report Nos. 50-400/79-06, 50-401/79-06, 50-402/79-05 and 50-403/79-05 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 S
aron H rris Site near Raleigh, North Carolina Inspector:
R.
D.
$
Approved by:
A. R. Herdt, Section Chief, RCES Branch D te i ed te Signed SUMMARY Inspection on April 2-5, 1979.
Areas Ins ected This routine unannounced inspection involved 31 inspector-hours on site in the areas of project status; licensee action on previous inspection finding; licensee identified item; posting of 10CFR21 notices; IE Bulletins, Circulars and Information Notices; construction contract. review; and a walk-through inspection of the power block, storage yard number 12, west auxiliary dam, spillway, and separating dike.
Results Of the five areas inspected, no apparent items of noncompliance or deviation were identified.
> 90525 0 0&c
~DE ILE 1.
Persons Contacted Licensee Em lo ees S.
-T.
-R.
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- G R.
D. Smith, Manager, Power Plant Construction Department H. Wyllie, Manager, Nuclear Construction Section M. Parsons, Site Manager J. Chiangi, Manager, Engineering and Construction, gA M. I,ucas, Resident Engineer L. Forehand, Principal gA Specialist Hanford, Principal Engineer, Other licensee employees contacted included 2 construction craftsmen,
site engineers, and a licensing engineer.
Other Or anizations
- W. D.
Goodman, Daniel Construction Company Project Manager-Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on April 5, 1979, with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Ins ection Findin s (Open) Noncompliance No. 400, 401/79-02-01, Lack of Document Control.
The inspector held discussions with the office engineer, lead area engineer, and principal gA specialist, and reviewed the licensee's draft response,and the associated procedural changes implemented on March 19,'979.
This item will remain open pending receipt of the licensee's formal response and review of corrective measures following the estab-lished date of full implementation.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inde endent Ins ection Effort a.
Project Status and Site Inspection On April 2, 1979, the inspector conducted a walk-through inspection of the site which included observation of construction activities
in the power block area, west auxiliary dam and spillway, west auxiliary separating dike, and storage yard number 12.
Seismic hanger installation has begun in the reactor auxiliary building and protective coatings are being applied to portions of the pipe tunnel walls of the fuel handling building.
Chicago Bridge and Iron has completed erection of the Unit 1 containment twelfth wall liner ring and installation of reinforcing steel and erection of formwork has begun on the primary shield wall.
Drilling and blasting is continuing in the downstream portion of the main dam spillway.
All required mapping in the west auxiliary dam core trench and rock fillembankment areas has been completed and Class D dental concrete has been placed as required in the core trench.
The combined work force now totals some 3,370 people.
Steam Generator Rotation There are presently six Westinghouse steam generators at the Harris site in storage yard number 12 for Units 1 and 2.
To facilitate access for a planned modification to these generators by Westinghouse, CPSL will raise and rotate the generators in their present storage location.
Hydraulic jacks have been obtained and will be utilized to lift the generator off its two storage saddles after the jacks have been load tested again at the site.
The vessel will be raised approximately 42" to provide manway entry and clearance.
A 60 ton crane with a sling and shackle arrangement will be used to rotate the vessel on two greased plywood sheets sandwiched together at each saddle.
The inspector held discussions with the CP 8 L resident engineer and responsbile site engineer, reviewed a draft copy of the con-trolling work procedure, and examined the schedule for work activities.
Region II surveillance will continue as Westinghouse directs the modification to install auxiliary feedwater nozzles in each generator.
Plant Construction Responsibilities A review was made of the plant construction contract and its eleven supplemental orders between Carolina Power and Light (CPGL) and Daniel Construction Company (DCC).
The contract was orginally issued on May 26, 1972, and provides for construction of the four unit plant consisting of the power block, turbine buildings, circulating and service water systems, service buildings, and portions of the switchyards.
Construction activities involving
site clearing, lake channels, separating dikes, dams, pump stations, spillways and bridges are not within the scope of the DCC contract.
Codes, regulatory guides and standards applicable to construction are identified in the PSAR and imposed by CPM, gA manuals and architect-engineer specifications.
CPGL retains full control and responsibility for completion of the project in accordance with the terms and conditions of its NRC application and construction permit.
DCC is obligated to adhere to CPM,'s overall gA program requirements and is subject to the requirements of 10 CFR 21.
DCC is providing qualified personnel to CPM for inspection and nondestructive examination; however, these personnel are recertified by and report to CPGL.
In areas covered during this independent inspection effort, no items of noncompliance or deviations were noted.
6.
Licensee Identified Item Prior to this inspection, the licensee had identified the following item under
CFR 50.55(e):
(Closed)
Item (400/79-02-03),
Steam Generator and Reactor Coolant Pump Embedment Plate Welds.
The licensee's interim report of February 12, 1979 stated that the subject potentially reportable deficiency was still under evaluation as related to reportability under the requirements of
CFR 50.55(e).
On March 19, 1979, CP 6 L advised Region II that the deficiency had been determined to be nonreportable.
During this inspection, the inspector held discussions with the site principal gA specialist, site resident engineer, and a materials engineer.
A review as made of the architect-engineer's load analysis, the CP 6 L Materials Science Laboratory destructive examination report, minutes of the meeting between CP 6 L, its architect-engineer, and the affected supplier, the drawings involved, and CP 6 L's final report on the deficiency.
It was determined that the evaluation conducted by the licensee was thorough and personnel were knowledgeable of the deficiency and its implications.
The inspector concurs with the licensee's determination in that the architect-engineer's analysis concludes that the anchorages as provided.
would be capable of handling loads under all loading conditions with actual stresses far below those permitted by the existing codes and regulatory guides.
The nine affected anchor plates have been scrapped.
7.
IE 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
-4-applicable documents had been received, appropriate action was being taken, and a proper response date had been established, as required.
a.
(Closed)
IEB 78-02, Terminal Block Qualification" (Units 1-4)
The licensee's supplemental response dated February 15, 1979, was received and reviewed by the inspector.
As noted in Inspection Report 400-403/78-03, CPS's evaluation was continuing in the area of mechanical components procured by its architect-engineer, and components supplied by the nuclear steam supply system supplier.
This investigation is now complete and it has been determined that no unprotected safety related terminal blocks are scheduled for use in any systems within the containment that must function in a post-accident environment.
b.
(Open)
IE Circular 78-08, "Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants" (Units 1-4)
The inspector was advised by the Nuclear Licensing Unit that work is continuing on the examination requested by the subject circular.
Region II will continue to monitor this activity until such time as CPSL's examination and report previously noted in Inspection Report 400-403/
78-07 is completed.
8.
CFR 21 Postin Re uirements The site facilities were inspected to determine if the posting require-ments specified in 10 CFR 21.6 were continuing to be implemented.
The licensee had posted notices prepared per
CFR 21.6(b) in locations frequented by administrative, engineering, and craft personnel.
The posting requirements of 10 CFR 21 as implemented by CPM 's "Procedure for Evaluating and Reporting of Defects and Noncompliance in Accordance with 10 CFR 21,",are continuing to be implemented at Shearon Harris Nuclear Power Plant.
No items of noncompliance or deviations were identifie ~
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