IR 05000400/1978009

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IE Insp Repts 50-400/78-09,50-401/78-09,50-402/78-09 & 50-402/78-09 on 781205-08.No Noncompliance Noted.Major Areas Inspected:Project Status,Licensee Action on Previous Insp Findings,Concrete Placement in Containment & Warehousing
ML18003A367
Person / Time
Site: Harris  Duke Energy icon.png
Issue date: 12/18/1978
From: Bradley R, Herdt A, Wilcox J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18003A363 List:
References
50-400-78-09, 50-400-78-9, 50-401-78-09, 50-401-78-9, 50-402-78-09, 50-402-78-9, 50-403-78-09, 50-403-78-9, NUDOCS 7901180111
Download: ML18003A367 (10)


Text

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(4 Po UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30303 Report Nos.:

50-400/78-09, 50-401/78-09, 50-402/78-09 and 50-403/78-09 Docket Nos.:

50-400, 50-401, 50-402 and 50-403 License Nos.:

CPPR-158, CPPR-159, CPPR-160 and CPPR-161 Categories:

A2, A2, A2 and A2 Licensee:

Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name:

Shearon Harris Nuclear Power Plant Units 1, 2, 3 and

Inspection at:

Shearon Harris Nuclear Power Plant, Wake and Chatham Counties, North Carolina Inspection Conducted:

December 5-8, 1978 Inspectors:

R.

D. Bradley J. P. Wilcox Jr.

Revieved by:

LAITY4iGgi A. R. Herdt, Chief Projects Section Reactor Construction and Engineering Support Branch idio'b Date Ins ection Summar Ins ection on December 5-8 :1978 (Re ort Nos. 50-400/78-09 50-401/78-09 50-02 78-09 and 50- 03 78-09 finding; concrete placement in Unit 1 containment; warehousing; inspector followup item; licensee identified items; QA record storage facilities; and the review of QA manual procedures for safety-related structural steel and supports.

This inspection involved 58 inspector-hours on'ite by two NRC inspectors.

Results:

No items of noncompliance or deviations were identified.

V90$486'i(i

82; V)8V

RII Rpt. Nos. 50-400/78-09, 50-401/78-09, 50-402/78-09 and 50-403/78-09 I-1 DETAILS I Prepared by:

.e'.

D.

radley, r.,

i cipal Inspector Projects Section Reactor Construction and Engineering S

o t ranch t J.

D. Wilcox, Jr., Reactor inspector l7 Projects Section Reactor Construction and Engineering Support Branch ate

~g /8 75 ate Dates of Inspec

'og:

December 5-8, 1978 Reviewed by:

l'.

R. Herdt, Chief Projects Section Reactor Construction and Engineering Support Branch

/2 4 78'te 1.

Persons Contacted a.

Carolina Power and Li ht Com an (CPSL)

-"S. D. Smith, Manager, Power Plant Construction Department

"T. H. Wyllie, Manager, Nuclear Construction Section-R.

M. Parsons, Site Manager-A. Lucas, Resident Engineer

"-G. L. Forehand, Principal (}A Specialist, Site Unit-L. E. Jones, Principal gA Specialist, Engineering QA Unit J. Carter, Civil Engineer, Mechanical Unit G. White, Materials Engineer, Codes and Standards Unit b.

Chica o Brid e and Iron (CB&I)

"R. Ferguson, Corporate gA-P. Hazelip, Project Welding and gA Superintendent c.

Daniel Construction Com an

  • W. D.

Goodman, Construction Manager The inspectors also interviewed thirteen other employees during the course of the inspection.

They included licensee gA specialists and technicians, civil and code and standards e

RII Rpt. Nos. 50-400/78-09, 50-401/78-09, 50-402/78-09 and 50-403/78-09 I-2 engineers, warehouse supervision, and contractor rodbuster foremen and concrete foremen.

-Denotes those present at the exit interview.

2.

Licensee Action on Previous Ins ection Findin s

(Closed)

Noncompliance No.

400/78-06-01, Incomplete Daily Weld Material Distribution Log

-

CPSL's letter of response dated November 22, 1978, has been reviewed and determined to be acceptable by Region II.

The inspectors held discussions with the CPRL Principal (}A Specialist, Senior Civil QA Specialist, CB&I Project Welding and QA Superintendent, and Construction Superintendent, and examined the corrective actions as stated in the letter of response.

The inspectors concluded that CPM had determined the full extent of the subject noncompliance, performed the necessary survey and followup actions to correct the present conditions, and developed the necessary corrective actions to preclude recurrence of similar circumstances.

The corrective actions identified in the letter of response have been implemented.

3.

Unresolved Items No new unresolved items were identified.

Inde endent Ins ection Effort a

~

Project Status and Site Inspection The inspectors conducted a walk-through inspection of the site which included observation of concrete placement and welding activities for Unit 1 containment, re-bar erection activities in the Reactor Auxiliary Common Building for Units

and 2,

and warehouse storage and control.

Reinforcing steel installation has started for the Unit

containment interior base mat with installation of the lower radial bars.

Liner erection is currently 24$ complete.

In the areas covered during this independent inspection effort, no items of noncompliance or deviations were note RII Rpt. Nos. 50-400/78-09, 50-401/78-09, 50-402/78-09 and 50-403/78-09 I-3 b.

Concrete The inspectors monitored initial placement activities for the Unit

Containment Building exterior wall pour at elevation 218.5'.

The first batch testing for air content, slump, and temperature for placement number 1CBXW219001 on December 6, 1978, was witnessed by the inspectors.

Pumps were used for pour placement with samples being taken at pump discharge.

A new slickline system with manually operated discharge gate valves positioned around the containment circumference was being utilized.

Personnel were stationed within the upper wall section so that vibrators could be effectively utilized in the narrow placement area.

A total of 240 yards were scheduled for placement.

c.

QA Record Storage Facilities The inspectors made a surveillance inspection of the QA Record Storage Facility including the following: controls and security of records, sign-in/sign-out logs, availability of specific records, record identification, record review, record storage and preservation, and fire protection provisions.

d.

NRR/DSE Inspection of Geological Features at Main Dam On December 8,

1978, the inspectors participated as observers during an NRR site inspection of the main dam schistose zone at Station 2+50 and the core trench exposures of faults A through D.

Region II's attendance during the inspection was to familiarize the inspectors with the geologic aspects of the main dam area as well as coordination of inspection effort between OIE and NRR.

5.

Review of A Manuals for Structural Steel and Su orts The inspectors reviewed all the documents listed in paragraph 5 of IE Inspection Report No. 50-400,401,402,403/78-08 to determine whether adequate procedures and facilities have been established to assure that structural steel and support activities such as hold point inspection, receiving inspection, storage, identification, and installation will be accomplished in accordance with the QA program requirements.

No items of noncompliance or deviations were note RII Rpt. Nos. 50-400/78-09, 50-401/78-09, 50-402/78-09 and 50-403/78-09 I-4 6.

Licensee Identified Items Prior to this inspection, the licensee identified the following items under 10 CFR 50.55(e):

a.

(Closed) Items (400/78-08-08, 401/78-08-08, 402/78-08-08, 403/78-08-08):

Studs Separating from Steel Plates During Handling.

CPSL advised Region II by telephone on November 'll, 1978, that the subject potentially reportable deficiency had been determined to be nonreportable.

The inspectors held discussions with the site principal QA specialist, site resident engineer, and a materials engineer from the corporate office Code and Standards Unit.

Accumulated test results and correspondence was examined and it was determined that the evaluation conducted by the licensee was thorough and personnel were knowledgeable of the deficiency and its implications.

The inspectors concur with the licensee's determination and have no further questions at this time.

b.

(Closed)

Item (400/78-08-09):

Water Membrane Leakage in Unit

Containment.

The licensee's interim report of November 22, 1978, stated that the subject potentially reportable deficiency was still under evaluation as related to reportability under the requirements of

CFR 50.55(e).

On December 1,

1978, CPM.

advised Region II that the deficiency had been deter'mined to be nonreportable.

During this inspection, the inspectors talked with the site principal QA specialist, site resident engineer, and a civil engineer from the corporate office Mechanical Unit.

Spectrographic tests have been performed and analyzed on the accumulated sump water, piezometric data has been compiled and evaluated, and RAB 190 sump levels are being monitored.

CPM, has determined that the accumulated sump water is primarily ground water and that the containment building porous concrete channel collection system is operating as expected, and its four sumps will be designed such that they will be capable of removing any water which may find its way inside the membrane (reference PSAR Section 5.1.1.8.4d).

Region II concurs that this deficiency is nonreportable in that under the conditions reported, the water collection system is functioning as designed to.prevent hydrostatic head on the exterior of the containment liner.

Region II has no further questions at this time.

7.

Ins ector Followu Items (Closed)

Inspector Followup Item No. 50-400,401,402,403/78-07-01, CDR Procedure Revision

-

The inspectors reviewed Revision 4 of the

RII Rpt. Nos. 50-400/78-09, 50-401/78-09, 50-402/78-09 and 50-403/78-09 I-5 licensee's procedure,

"Evaluating Deficiencies in Accordance With 10 CFR 50.55(e)."

The subject procedure has been revised to address the handling of potentially reportable deficiencies and was approved, and issued for use on December 5, 1978.

The topics of discussion referenced in paragraph 4.c of IE Inspection Report 50-400,401,402,403/78-07 have been incorporated into the subject procedure and Region II has no further questions at this time.

8.

Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection.

The inspector summarized the scope and findings of their inspection of actions on previous inspection findings, licensee identified items, and the review of QA manuals and documentation storage facilities.

No items of noncompliance or deviations were note