IR 05000400/1982013
| ML20053B161 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/30/1982 |
| From: | Burger C, Maxwell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053B155 | List: |
| References | |
| 50-400-82-13, 50-401-82-13, NUDOCS 8205280128 | |
| Download: ML20053B161 (6) | |
Text
- e UNITED STATES 8"
N NUCLEAR REGULATORY COMMISSION
$
E REGION li d'[
101 MARIETTA ST., N.W., SUITE 3100 o,
ATLANTA, GEORGIA 30303
%
Report Nos. 50-400/82-13 and 50-401/82-13 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, llc 27602 Facility Name:
Shearon Harris Docket Nos. 50-400 and 50-401 License Nos. CPPR-158 and CPPR-159 Inspection at Shearon Harris site near Raleigh, North Carolina Y/
Inspector:
C
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n G. F. tiaxwell (/
Date Signed Approved by:
,f-t/rp s Y 70 M C. W. B~ urger, Sectjgn Chief, Division of
' 0 ate Figned j
Project and Resi' dent Programs SUf1 MARY Inspection on fiarch 20 - April 20, 1982 Areas Inspected This routine, announced inspection involved 95 resident inspector-hours on site in the areas of coatings, concrete, storage, and environmental meetings.
Resul ts Of the four areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- R. ft. Parsons, Site fianager
- G. L. Forehand, Director QA/QC
- A. ft. Lucas, Senior Resident Engineer
- D. C. Whitehead, Senior QA Specialist Other Organizations
- W. D. Goodman, Daniel Project fianager
- Attended exit interview 2.
Exit Interview
The inspection scope and findings were summarized on April 19, 1982, with those persons indicated in paragraph 1 above.
I 3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
S.
Coatings - Unit 1 Containment Building a.
The inspector, accompanied by an assigned CP&L QA representative, observed the handling and mixing of service level I coating materials.
The observations were related to filler materials (NUTEC 11S) which were being made ready for use inside containment Unit 1 at elevation 261'.
Filler is the coating material which is utilized to fill in shallow surface irregularities on concrete surfaces prior to coating with the finish coat. The primer materials were being mixed for use on the liner plate at about elevation 261'.
The material, Keeler and Long 7107 primer, was checked by inspection personnel prior to use to assm e that the material was acceptable, the material shelf life had not been exceeded, a clean mixing area was established, and the mixing procedure was followed by coating personnel.
During the aforementioned observa-tions the inspector observed two containers lying near the loop "C" steam generator shield wall.
The containers were found to contain Concresive 1411 epoxy grout. The containers, part A and another part B, had been opened previously and exposed to the airborne dust and sandblasting materials lying on and around the containers. Tne con-tents of the containers were examined and found to contain foreign contaminants.
Concresive 1411 is a type of concrete surface patching material which is used to fill concrete tie holds, bug holes, and other
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abrupt irregularities greater than h" in diameter.
Foreign materials may jeopardize the adhesive ability of the two part mix and therefore the overall coatings system.
The NRC inspector discussed this condi-tion with responsible CP&L personnel. As a result, a Poor Practice Report was written. Also, CP&L QA personnel are making an effort to get the applicable procedures revised to require more controls over the use of Concresive epoxy grout, b.
The inspector reviewed Construction Inspection (Cl) daily coating records, interviewed CI coating inspectors and inspected the magnetic test equipment which is utilized in measuring the dry film thickness of coatings on the containment liner plate. As a result, it was observed that personnel are cognizant of coating procedural requirements and are documenting inspection results.
However, a review of the calibration practices that are utilized for testing the magnetic test equipment has not included checking the equipment through its full range.
The range of the equipment varies from 0 thousandth's of an inch (mils) to 40 mils and has been calibration tested from only 0 to 8 mils. CP&L expects that the magnetic test equipment may be utilized in the future,
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to measure readings greater than 8 mils. The inspector inquired as to why the magnetic test equipment has not been checked over its entire usable test range (0-40 mils). The inspector was informed that the test equipment had not been used to attain readings greater than 8 mils.
Further, calibration test standards have been ordered which cover 0-40 mils and the users of the equipment were informed not to utilize them to attain readings greater than 8 mils until the test devices have been calibrated through their entire range of potential use (0 to 40 mils).
Prior to the NRC exit meeting, the wider range test standards arrived at the site and all magnetic test gauges were calibra ted.
c.
The inspector, accompanied by responsible CP&L inspection personnel, observed the conditions of the surfaces of the containment liner plate at elevations 236' and 261' south and east. The inspector took random independent measurements of the cured surfaces to determine if the required amounts of primer materials were applied. As a result, the surfaces were found to be within the thickness recommended by the applicable work procedure (WP-107, section 4.7.2).
d.
During the above observations the following were referred to for requirements:
PSAR section 1.4, therefore Regulatory Guide 1.54; EBASCO specification CAR-SH-COR-02; construction procedures TP-04, TP-17, TP-29 and WP-107.
No violations or deviations were identified in the areas inspected.
6.
Concrete - Unit 1 a.
The inspector observed portions of concrete placements being made in Unit 1 fuel handling building (pour numbered 1FHXW295001, IFHSL216014
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and 1FHS!1206012) and pour numbered 1ACXW320003 in the reactor auxiliary common building. The above observations included the following:
(1) The condition of the concrete forms was inspected for cleanliness, level and tightness.
(2) Concrete placement activities were inspected as they pertained to delivery time, rate of rise, free fall and testing of the concrete at the point of delivery and consolidation.
(3) Construction inspection personnel were present to assure compli-ance with the specification and procedural requirements.
(4) Suitable weather protection was provided, as applicable.
b.
The inspector participated in portions of an inspection conducted by another RII inspector.
The inspection concerned concrete placement, testing and curing.
The results of the inspection are documented in RII reports numbered 50-400,401/82-12.
The following were referenced during the above observations:
PSAR section 1.4,1.8; design specification CAR-SH-CH-6; construction procedures WP-01, i
WP-05, WP-15, CQA-6, TP-15 and TP-17.
No violations or deviations were identified in the areas inspected.
7.
Storage and Other Areas Inspected - Units 1 and 2 a.
The inspector observed the stored conditions of Units 1 and 2 reactor vessels and Unit 2 steam generators. The storage conditions were evaluated to datermine whether requirements are being met as follows:
(1) The vessels and steam generators were stored in accordance with the procedural requirements.
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(2) The protective coatings on the vessels and steam generators were intact.
(3) The supports for the vessels and steam generators were adequate to prevent the entry of excessive dirt or water from accumulating in or around them.
(4) The supports for the vessels and steam generators were adequate to
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prevent shifting or collapse of the support structures.
b.
The inspector toured the outside piping laydown yard number 12.
During the tour, the stored conditions of the piping and equipment were evaluated to determine whether requirements are being met as follows:
(1) Piping and equipment, in general, were stored off the ground to prevent entry of dirt into them or contamination from environ-
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mental conditions.
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(2) The storage areas were identified sufficiently to provide identity and location as required by those who may be seeking the location of certain pipe spool pieces or equipment.
(3) The drainage, in general, was acceptable in areas where the piping spool pieces and tanks were stored.
(4) Access was adequate for placement or removal of pipe spool pieces and equipment.
c.
During a tour of Unit 1 reactor auxiliary building the inspector o
observed craftsmen working on electrical cable tray installations.
The inspector randomly selected ten drawings which were being utilized.
The drawings were evaluated for accuracy and usability.
The drawings were checked against the site document control master lists and were found to be of the most current revisions.
d.
During a tour of Unit 1 reactor auxiliary building at elevation 261'
the inspector observed that a seismic I electrical cable tray support was missing its field welds.
Close inspection of the hanger, piece numbered 77G5 on drawing 1364-34897 revision 1, revealed that it already had been inspected as having its welds completed and had been coated with the required coating materials.
The inspector inquired about the missing field welds and was informed that CP&L QC was aware of the welds not being made.
Subsequently, during a later tour of the same area, the inspector observed that the required field welds had been applied. The inspector has no further questions about this matter, at this time.
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e.
The inspector ineasured the size of several shop welds on the miscel-l laneous seismic I structural steel located in Unit I reactor building
at about elevation 246' near column F2. The measurements were taken on I
shop welds attached to steel pieces marked 15A3, 25A4-1, 25A4-2,15A5 and 25A10.
The steel was manufactured by Peden Steel Company and consisted primarily of w8 x18 "I" beams.
During the observations and evaluations the following were referred to:
PSAR section 1.4, construction procedures WP-106, AP-XIII-05, PGD-002, and AP-XIII-07; drawings numbered 1364-9845, 9826, 9835 and 34897.
No violations or deviations were identified in the areas inspected.
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8.
Environmental Meetings - Units 1 and 2 a.
On April 6 and 7,1982 the inspector attended, observed and participated in meetings between USNRC and CP&L.
The meetings were held as part of
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l the review process for preparing the environmental statement relating to the operating license application for both units. April 6 was spent primarily on site tours to make observations where the plant facilities and structures have an interface with the surrounding environment. The morning of April 7 consisted of a meeting between NRC staff, CP&L and local officials.
The afternoon of April 7, consisted of a short I
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meeting between the NRC staff and the responsible North Carolina
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representative for radiological controls.
j b.
On April 7, at about 7:00 p.m. until 10:00 p.m., the NRC held a meeting with the public.
The meeting was held for the purpose of allowing the
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NRC staff to hear any concerns which the public may have as they relate to the preparation of the environmental statement for both units.
The meeting was held at the senior high school in Apex, North Carolina.
During the meeting several concerns were offered by the public, some of which were not necessarily envircnmental in nature. The NRC staff responded to most of the concerns and informed the members of the meeting that the notes of the meeting would be presented to the local public document roan for the public's review.
No violations or deviations were identified in the areas inspected.
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