IR 05000483/1980024

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IE Insp Rept 50-483/80-24 on 800902-26.No Noncompliance Noted.Major Areas inspected:safety-related Const Activities Including Protection of Reactor Vessel & Other Components of NSSS
ML19338F843
Person / Time
Site: Callaway 
Issue date: 10/14/1980
From: Hansen W, Knop R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19338F842 List:
References
50-483-80-24, NUDOCS 8010270385
Download: ML19338F843 (9)


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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-483/80-24 Docket No. 50-483 License No. CPPR-139 Licensee: Union Electric Company P. O. Box 149 St. Louis, Mo 63166 Facility: Callaway, Unit 1 Inspection At: Callaway Site, Callaway County, M0

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Inspection Conducted: September 2-26, 1980

//,//4 b Inspector:

W. A. Hansen

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Approved By:

R. C. Knop

/d - /YM Projects Section 1 Inspection Summary Inspection on September 2-20, 1980 (Report No. 50-483/80-24)

Areas Inspected:

Routine inspection by the IE Regional Resident Inspector (RI) of safety-related construction activities including protection of the reactor vessel and other components of the nuclear steam system supplier; (NSSS), work on the core internal instrument tubes; material lay down and storage areas; electrical work; welding of reactor coolant system piping; drawing control; welding reinforcement steel; and concrete pours. This inspection involved 85 inspector hours by one NRC Inspector.

Results: No items of noncompliance or deviations were identified.

8010270375

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DETAILS

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Person Contacted

Union Electric Company (UE)

  • W. H. Weber, Manager Nuclear Construction
  • F. D. Fields, Quality Assurance Manager
  • M. E. Doyne, General Superintendent, Callaway Construction
  • R. L. Powers, Site Quality Assurance Group Leader
  • J. Laux, Quality Assurance Assistant Engineer

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J. R. Veatch, Quality Assurance Engineer S. Hogan, Quality Assurance Assistant Engineer P. W. Godt, Quality Assurarce Engineer J. L. Marden, Quality Assurance Consultant

  • C. Plows, Quality Assurance Consultant
  • H. Hess, Quality Assurance Consultant Daniel Internation Corporation (Daniel)
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J. Starr, Project Manager W. L. Sykora, Assistant Project Manager

  • J. A. Holland, Construction Engineering Manager J. R. Cook, Quality Control Manager M. Smith, Audit Response Coordinator The inspector also contacted and interviewed other licensee and contractor personnel, including craftsmen, QA/AC, technical and engineering staff members.
  • Denotes those attending at least one of the exit meetings.

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Functional or Program Areas Inspected 1.

Plant Tours One or more plant areas were toured several times each week during the reporting period to observe general construction practices; area cleanliness and storage condition of equipment, piping, and electrical cable.

Two tours were made on back shifts of work.

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2.

Electrical Cable Installation During the reporting period, the inspector observed work including a.

installation, handling, and protection of electrical cables. Speci-fically, work associated with these electrical cable pulls was observed:

(1) Cable Pull 263 Cables 4GNK03BA 4ENG02bc 4ENG02BD 4EJG09AC 4EJG09BC (2) Cable Pull 650 Cable 1SAZO2LC b.

For each of the pulls some or all of the following activities were observed:

(1) Pull cards were in use, (2) the cables were identified, (3) Quality Control inspections were performed and Quality Control personnel witnessed the pull.

On one occasion it was noted that Electrical Craftsmen were stepping on previously pulled cable. This condition was brought to the attention of the Licensee. Action was taken in training sessions to re-emphasize to Electrical Craftsmen that installed cable must be protected from work activities.

g, The method of supporting electrical cables in vertically

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' mounted raceways was reviewed. Presently the cables are tied

j in place and supported by plastic tie wraps around tray rungs.

Bechtel Drawing No. E0103Q (paragre.ph 5.3.9.2) discusses cable i

support in vertical cable trays and states that cables may be supported from building steel using Kellum gripes or from tray rungs. The drawing also refers to IEEE std. 422 paragraph 7.2.5 which states that vertically run cables be supported by holding devices in tray and be lashed or served at support points co keep the cable within the side rails. The Siesmic qualification data for plastic tie wraps is not available for review. Pending review of this data along with any installation instructions such as the number and type of cable allowed to be tied by a signie wrap, will be nn unresolved item.

(Item 483/80-24-01)

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Concrete Placement a.

During the reporting period, two concrete placements were observed.

(1) One placement consisted of UC306W36, W38, W39, W40, W42, W47 and W48 (Ultimate Heat Sink Pump Building)

(2) Placement 2C641W07 (Fuel Storage Building)

For each of the placements listed above, some or all of the following conditions were noted.

(a) The forms were secure, leak tight, and had been wetted prior to the placement.

(b) The preplacement inspection had been ecmpleted and was in order.

(c) Quality control inspectors were assigned to each crew in addition to those assigned to perform perd. odic concrete testing.

(d) Concrete testing was performed at the required frequencies.

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(e) Adequate numbers of crews and personnel were assigned to make the placement.

(f) The placement was satisfactory.

(g) Curing was monitored and found to be satisfactory.

No items of noncompliance or deviations were identified.

4.

Fabrication of Reactor Coolant Pressure Boundary and Safety Related Piping Systems a.

During the reporting period, the inspector observed work in-cluding handling, protection, inspection, and welding of reactor coolant pressure boundary and safety related piping systems.

(1) Reactor Coolant System Welds j

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2BB-05-F004 2BB-05-F003 2BB-15-F003 (2) Containment Cooling System 2GN-01-F022

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(3) Main Steam System 2AB-01-F050

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2AB-01-F026 2AB-01-F074 l-4-L l

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(4) Component Cooling Water System 2EG-10-F012A E7-14-FW18 (5) Containment Spray System

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2EN-02-FW60 For each of these welds one or more of the following fabrication activities was observed. Handling and protection cf piping and partially completed welds was satisfactory. Purge gas was correctly t

l used. The weld area was free of any grease or particles. The joint fit-up dimensions were within procedural requirements and the welders

were certified as qualified for the procedure specified to be used for welding the pipe joint.

The inspector observed the storage and segregation of welding materials. ~ he temperature of the ovens was correct and the

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issue and re: Arn of welding materials was controlled.

No items lof noncompliance or deviations were identified.

5.

Nuclear Steam System Supplier (NSSS) Equipment The inspector observed the inplace storage and protection of a.

NSSS components and piping. The piping assemblies, reactor vessel internals, and reactor vessel head is properly stored and protected, b.

The inspector observed the installation of an instrument guide tube assembly.

No items of noncompliance or deviations were identified.

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Piping System Nondestructive Testing a.

During the reporting period the inspector observed non-destructive testing (Liquid Penetrant) of weld F-407 in Reactor Coolant System loop 4.

(1) The surface of the weld was satisfactory for the l

performance of liquid penetrant examination.

(2) The technique was satisfactory and was performed by a qualified inspector.

No items of noncompliance or deviations were identified.

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Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. One unresolved item disclosed during this inspection is discussed in paragraph 2 Exit Meetings The resident inspector attended an September 19, 1980 exit meeting conducted by RIII inspector E. Lee.

The inspector met with licensee representatives (denoted under Persons Contacted) on September 11,19, and 26, 1980. The inspector summarized the scope and findings of the inspections performed. The licensee representatives acknowledged the findings reported in previous paragra shs.

Attachment: Preliminary Inspection Findings

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OTTI CE OF 155FECT;05 AMD ' E::T;d.0;;:. ;-

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pKELIMINARY IN5?ECTION FI!;DINOS I

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REGIONAL OFFICE

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Nuclear Regulatory Con =ission, Region III

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Office of Inspection and Inforcenent

!;. ".. ; ; 3. *:u s curi 799 Roosevelt head Glen Ellyn, Illinois 60137

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!.. LICENSE NL'MEIRS 5.

DATE OF 155FECTIOS

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V1:ni :he sce;e of the inspection, no ite=s of noncorpliance or deviatien vere f:end.

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T e f:'" r -ing n2:ters are preliminary inspe : ion findings:

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T..ese preli=inary inspection findir.gs vill be reviewed by NRC Supervision /

l ha.1;ensn: at :he Region III Office and they vill correspond with you

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a.y enforcenent action.

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CTF1 CE OF IN5PECTION ANL ESTO.CE:'E::~

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PRELIMINARY INS?ECTION FINDINOS I

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REGIONA.,, O ICE r:

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';uclear Regulatory Commission, Region !!!

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l.ICENSE NLTsERS 5.

DATE OF INS?ECTION

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'ti..in the secpe of the inspection, no ite=s of nenco:pliance or deviation

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Tne f:'.'.cving n.s:ters are preliminary inspection findings:

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7..ese prel1=inary inspec: ion findings will be reviewed byf NRC Supervision /

Pz agenen: at the Region III Office and they will correppend with you

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office of Inspection and Enforcenen; i, *... 3.

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here p elf _ intr / inspe::i:: findings will be reviewed by NRC Supervisi n/

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