IR 05000400/1979008
| ML18017A547 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/22/1979 |
| From: | Bradley R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18017A545 | List: |
| References | |
| 50-400-79-08, 50-400-79-8, 50-401-79-08, 50-401-79-8, 50-402-79-08, 50-402-79-8, 50-403-79-07, 50-403-79-7, NUDOCS 7907050189 | |
| Download: ML18017A547 (8) | |
Text
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~4 UNITEDSTATIS NUCLEAR REGULATORYCOMMISSION RKOION II 101 MARIETTASTREET, NPt.
ATLANTA,OEOROIA 30303 Report Nos. 50-400/79-08, 50-401/79-08, 50-402/79-07 and 50-403/79-07 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name:
Shearon Harris Nuclear Power Plant License Nos.
CPPR-158, CPPR-159, CPPR-160 and CPPR-161 Inspection at Sh ron H ris site near Raleigh, North Carolina Inspector:
R.
D. Bradle ate Signed Approved by:
A.
. Herdt, Section Chief, RCSES Branch ate Signed Inspection on April 23 - 27, 1979 This routine, unannounced inspection involved 36 inspector-hours in the areas of project status; licensee action on previous inspection findings; licensee identified items; steam generator modification; concrete placement; review of QA manual procedures for nondestructive examination; and a walk-through inspec-tion of the power block, storage yard number 12, west auxiliary dam, spillway and separating dike, and the main dam.
Results Of the six areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee E
lo ees
+T. H. Wyllie, Manager
, Nuclear Construction Section
- R. M. Parsons, Site Manager
- N. J. Chiangi, Manager, Engineering 8 Construction QA
- A. M. Lucas, Resident Engineer
- G. L. Forehand, Principal QA Specialist Other licensee employees contacted included three construction superin-tendents, five concrete inspectors, and two senior QA specialists.
Other Or anizations P.
K. Harris, Daniel Construction Document Control Supervisor J.
M. Given, Lumbermen's Mutual - Authorized Nuclear Inspector A. L. Arnold, Westinghouse, Tampa Division, Welding Engineer P. Smith, Heat Engineering, Vice President
+Attended exit Interview 2.
Exit Interview The inspection scope and findings were suamarized on April 27, 1979, with those persons indicated in Paragraph 1 above.
Insufficient time remained for the inspector to review the licensee's proce'dures on pro-tective coatings.
However, copies were requested and the licensee was advised that these will be examined during a subsequent inspection.
3.
Licensee Action on Previous Ins ection Findin s I
(Closed)
Noncompliance No. 400, 401/78-08-03, Failure to Calibrate Fine Aggregrate Sieves.
The inspector reviewed the licensee's actions to include sieve calibration activities under the site calibration program as discussed in inspection report number 50-400, 401/79-02.
Discussions were held with the senior civil QA, specialist, an examination of the comparator reticle certifications and four exhibits to Technical Procedure 04 was performed, and methods for recalling items for recalibration were reviewed and discussed with the QA records clerk.
Reticle certifications reflect traceability of master equipment to an NBS standard and Technical Procedure 04 now includes the reticles under the site calibration progra (Closed)
Noncompliance No. 400, 401/79-02-01, Lack of Document Control.
The licensee'a response of April 6, 1979 was reviewed and discussions were held with site management and the document control supervisor.
The corrective measures have been implemented as stated.
As previously reported in inspection report number 50-400, 401/79-06, procedural changes have been made and implemented methods for ensuring closeout of change notices have now been established in a new administrative procedure.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inde cadent Ins ection a.
Project Status During this visit, the inspector conducted a walk-through inspection of the site which included observation of concrete placement at the unit 1 tank building, rebar installation in unit 1 containment and the auxiliary building, diversion conduit activities at the main dam and construction status of auxiliary dam and separating dike.
Total concrete placed to date totals 230, 283 cubic yards with reinforcing steel quantities totaling in excess of 27,000 tons.
The combined work force is presently at 3,400 persons.
Two valve chambers have been set in the unit 2 containment building, and rock cleanup and form-work erection activities were underway for seal mat application in the unit 3 and 4 auxiliary building area.
b.
Concrete Placement Activities The inspector arrived onsite April 23, 1979, and monitored place-ment activities underway during a backshift inspection, Placement number ITKSL236001 for the unit 1 tank building basemat was in progress with 669 yards of a
1600 yard pour already placed.
A 4,000 pound M-44 mix was being used and the licensee was utilizing a creter crane and two pumps for placement.
Concrete tests were being made at truck discharge at the creter crane and at pipe line discharge for pumped concrete.
Air and slump values were within specified limits although a review of records indicated air content problems had been encountered earlier with the questionable concrete being rejected.
c ~
Steam Generator Modification As discussed earlier in inspection report 50-400, 401/79-06, westing-house is modifying six steam generators at the Harris site by installing auxiliary feedwater nozzles.
This modification is being performed as an extension of the vendor shop (Tampa) work.
The I
Tampa Inspection Point Program (IPP) is currently being established for process control.
Field work will be directed by the assigned W
Tampa Welding Engineer, and welding and heat treating will be performed by Heat Engineering, a
W subcontractor.
QA is the respon-sibility of the W Tampa Division and will be performed in accordance with the IPP.
CPM. will be performing nondestructive examinations and overall site surveillance functions.
The inspector reviewed the controlling documents, held discussions with CPK, W, and Heat Engineering personnel, and examined preliminary work activities underway.
Additional Region II monitoring of work activities will continue when modification efforts are fully underway.
6.
g No items of noncompliance or deviations were noted during the above independent inspection.
The inspector reviewed the documents listed below and discussed with responsible COL personnel the associated QA program work in the area of nondestructive examination related to welding of safety related structures and piping.
The review confirmed that adequate QA plans, instructions and procedures for specific safety related activities have been established in the QA manuals and that these documents conform to the QA program as described in Section 1.8 of the PSAR.
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), Construction QC Instructions (QCI), Ebasco and CPSL Site Specifications, and the Site NDE Manual were reviewed as typical of the applicable documents:
CQA-1 Personnel Training and Qualification CQA-2 QA Document 'Control CQA-4 QA Records CQA-5 Document Reviews CQC-1 Tool and Measuring Device Control CQC-2 Noncompliance Control CQC-6 Receiving Inspection CQC-19 Weld Control CQC-20 Post Weld Heat Treatment Control QAAP-1 Procedure for Corporate Audits QAAI-1 Corporate Procedures for QA Audit Documents AP-IV-03 Preparation, Approval, 6 Control of Procedures TP-04 Calibration of Controlled Tools TP-17 Construction Inspection Noncompliance Control QCI-101.1-Calibration of Macbeth'Film Densitometer
QCI 101.2 Field Calibration Check of Radiographic Penetrations gCI 301.1 Functional Check of Prod-Type Magnetic Particle Test Equipment CAR-SH-ME-ll Examination
& NDT Requirements for - Piping Systems, Materials, Welds and Components SHNPP Site Spec.
No.
NDE Visual Inspection
& Tempting Requirements for Code Class 1, 2,
BOP Piping Systems SHNPP NDE Manual No items of noncompliance or deviations vere identified.
7.
Licensee Identified Items Near completion of the inspection on April 27, 1979, the inspector vas informed by the licensee of a potential
CFR 50.55 (e) item.
A CP&L audit of Vestinghouse disclosed that impact tests on reactor coolant pump main flange bolts had been conducted by a Vestinghouse vendor in excess of code specified temperature values.
The bolts vere procured to the Suaaer 1972 Addenda of the ASME Code vhich specifies a 40F maximum for ijspact testing.
The Mestinghouse specification required
F or lover.
The bolts vere actually tested at 60-68F.
This item has been identified as Item 400, 401/79-08-01, Mestinghouse RC Pump Bolts Impact Tested Above Specified Temperature.