IR 05000424/1985026

Insp Repts 50-424/85-26 & 50-425/85-25 on 850608-0719.No Violations or Deviation Noted.Major Areas Inspected:Qa Containment Dome Reinforcing Steel & Tendon Sheathing, Reactor Vessel,Ie Info Notices & Bulletins & ACRS Meeting

ML20133N976
Person / Time
Site:	Vogtle
Issue date:	08/02/1985
From:	Rogge J, Sanders W, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133N970	List: IR 05000424/1985026 ML20133N967
References
50-424-85-26, 50-425-85-25, IEB-83-05, IEB-83-5, IEIN-85-015, IEIN-85-019, IEIN-85-025, IEIN-85-15, IEIN-85-19, IEIN-85-25, NUDOCS 8508140081
Download: ML20133N976 (12)

Text

e

'

, .

52 4cg UNITED STATES Do NUCLEAR REGULATORY COMMISSION

[

, REGloN 11 g j 101 MARIETTA STREET, * t ATLANTA, GEORGI A 30323

\...../

Report Nos.: 50-424/85-26 and 50-425/85-25 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-424 and 50-425 License Nos.: CPPR-108 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Conducted: June 8 - July 19, 1985 Inspectors: M m b W. F. Sanders, Senior Resident

~

Date S'igned Inspector, Co ruction Lbb 4 N&L J. F. Rogge, Senior Resident Sh}igned Da'te

Inspector, Operations Accompanying Personnal: . J. Schepens, Resident Inspector, Constryction Approved By: km _

S *L- [f[

M.~ V.' 51nTule, ection Chief Dato Signed i

Division of Reactor Projects SUMMARY Scope: This routine, unannounced inspection entailed 372 resident inspector-hours on site (75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> were on backshifts) inspecting: quality i assurance; containment dome reinforcing steel and tendon sheathing; VSL platform  ;

installation; reactor coolant system primary loop piping installation and '

welding; safety-related piping installation and welding; reactor vessel, upper and lower internals, integrated head package and safety-related equipment storage and protection; IE Information Notices; and IE Bulletin The inspectors also attended the ACRS subcommittee meeting on July 18 and 19, 198 Results: No violations or deviations were identifie \

8508140081 850802 PDR ADOCK 05000424 G PDR

- i

'

• .

.

REPORT DETAILS Persons Contacted Licensee Employees D. O. Foster, Vice President and Project General Manager P. D. Rice, Vice President and General Manager, W. T. Nickerson, Deputy Project General Manager W. C. Ramsey, Readiness Review Manager H. H. Gregory III, General Manager Nuclear Construction M. H. Googe, Project Construction Manager G. Bockhold, Jr., General Manager Nuclear Operations 0. Batum, General Manager Engineering and Licensing C. W. Hayes, Vogtle Quality Assurance Manager C. E. Belflower, Quality Assurance Site Manager - Construction

• E. D. Groover, Quality Assurance Site Manager - Construction S. D. Haltom, Quality Assurance Engineering Support Supervisor W. E. Mundy, Quality Assurance Audit Supervisor J. E. Sanders, Project Construction Manager - Unit 1 D. M. Fiquett, Project Construction Manager - Unit 2 B. C. Harbin, Manager Quality Control J. L. Blocker, Assistant Quality Control Manager T. L. Weatherspoon, Assistant Quality Control Manager

• A. McCarley, Project Compliance Coordinator

• C. Gabbard, Assistant Project Compliance Coordinator J. O. Dorough, Administrative Manager S. J. Piedra, QA Engineer Other licensee employees contacted included craftsmen, technicians, supervision, engineers, inspectors, and office personne Other Organizations F. B. Marsh, Project Engineering Manager - Bechtel M. Malcom, Deputy Project Engineering Manager - Bechtel D. L. Kinnsch, Project Field Engineering - Bechtel D. W. Stroham, Project Quality Assurance Engineer - Bechtel R. J. George, Mechanical Discipline Manager - Bechtel G. H. Fredy, Project Field Engineer / APE - Bechtel G. Introcaso, Administration Manager - Pullman Power

. *J. Mamon, Project Field Engineering, Q.E. - Bechtel D. R. Murphy, Construction Engineer - Oglethorpe Power Corporation

• Attended Exit Interview Exit Interview (30703C)

The inspection scope and findings were summarized on July 17, 1985, with those persons indicated in paragraph 1 above. The inspector described the j

- _ __ _

,

<

.. .

areas inspected and discussed in detail the inspection findings listed below. No dissenting comments were received from the license (0 pen) Inspector Followup Item 50-424/85-26-01 & 50-425/85-25-01 " Boron Injection Tank Description and Operation" - Paragraph (0 pen) Inspector Followup Item 50-424/85-26-02 & 50-425/85-25-02 " Review Licensee Action on Information Notice No's. 85-15, 85-19, and 85-25" -

Paragraph 1 (Closed) IEB No. 83-05: "ASME Nuclear Code Pumps and Spare Parts Manufactured by the Hayward Tyler Pump Company", Units 1 and 2 - Paragraph 1 The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters (92702)

Not inspecte . UnresolvedItems(92701)

Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviations. Unresolved items were not identified during this inspectio inspectio . Construction Inspection - Units 1 & 2 (92706C)

Periodic inspections were made throughout this reporting period in the form of general type inspections in different areas of both facilitie The areas were selected on the basis of the scheduled activities and were varied to provide wide coverage. Observations were made of activities in progress to note defective items or items of noncompliance with the required codes and regulatory requirements. On these inspections, particular note was made of the presence of quality control inspectors, supervisors, and quality control evidence in the form of available process sheets, drawings, material *

identification, material protection, performance of tests, and housekeepin Interviews were made with craft personnel, supervisors, coordinators, quality control inspectors, and others as they were available in the work area The inspectors reviewed the following drawings / documents to determine if system operation, construction and description meet regulatory design criteria:

-

FSAR Section 6.3.2.2.2, Boron Injection Tank Description

- . - - .,.-- - . .

- - - . - . - . . - - - . - . _ - - . . _ . - .-..

. __

.

.

.

1

-

FSAR Table 6. 3. 2.-3 , Motor Operated Isolation Valves in the Emergency Core Cooling System

-

FSAR Figure 6.3.2-1, Safety Injection System P&ID Drawing N IAX4DB119, Rev. 5

-

Bechtel Drawing R IX4DB119, Rev. 11, Safety Injection System i

'

P&ID

-

Draft Technical Specifications During this review, it was noted that the FSAR description and figures .

did not reflect the current construction desig Discussion with the I licensee representatives indicated that the design changes were being reviewed for FSAR updat The following items summarize the major system differences:

-

Heat tracing has been eliminated due to lower boron concentratio The Boron Recirculation System will be i solated from the Boron Injection Tank (BIT)

-

Inlet valves to the BIT will be opened and de-energized thus maintaining the BIT at full discharge pressure of the charging pump The inspectors indicated that additional review will be necessary pending the licensee's final determination on how the system will be operate This item is identified as an Inspector Followup Item 50-424/85-26-01 and 50-425/85-26-01 " Review Boron Injection Tank Description and Operation".  ;

No violations or deviations were identifie . Containment (Structural Concrete) - Unit 2 (47053C) Procedure and Document Review The inspector reviewed and examined implementation portions of the following procedures pertaining to the placement of concrete to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee commitment CD-T-02, Rev. 14 Concrete Quality Control

-

CD-T-07, Rev. 7 Embed Installation and Inspection

-

CD-T-06, Rev. 9 Rebar and Cadweld Quality Control

-

CD-T-20, Rev. 6 Installation and Inspection of Trumpets Rigid Extensions, and Duct Sheathing

-

2X2-001A002, Rev. 11

-,,-.,% ~w ,-e.e,---,,--,3 . . - = . . ., ,p, , - . . , r---,me-*,..y ,.w.--e,-rme --.---.m ,-%,y--- ge--.-m.--- ,*-e-g,~ ,=*-e-+ . - - -

_w-we-wv-

__ _

. .

.

l

.

b. Installation Activities The inspector witnessed portions of concrete placement indicated below to verify the following:

(1) Forms, Embedment, and Reinforcing Steel Installation

-

Forms were properly placed, secure, leak tight and clea Rebar and other embedment installation was installed in accordance with construction specifications and drawings, secured, free of concrete and excessive rust, specified distance from forms, proper on-site rebar bending (where applicable) and clearances consistent with aggregate siz (2) Delivery, Placement and Curing '

-

Preplacement inspection was completed and approved prior to placement utilizing a Pour Card (Exhibit CD-T-02*18).

-

Construction joints were prepared as specifie Proper mix was specified and delivere Temperature control of the mix, mating surfaces, and ambient were monitore Testing at placement location was properly performed in accordance with the acceptance criteria and recorded on a Concrete Placement Pour Log (Exhibit CD-T-02*20).

-

Adequate crew, equipment and techniques were utilize Inspections during the placement were conducted by qualified personne Curing temperature was monitore (3) Installation of Trumpets, Tendon Sheaths and Anchorage Components Trumpets, sheaths and anchorage components were oriented properly, installed within specified tolerances, clear and free of damag .

(4) Observed the Pulling of a Rabbit Through Horizontal Tendon No' and 154 Prior to Placement of Pour No. 2-010-038 (5) Observed the Pulling of a Rabbit Through Horizontal Tendon No' , 3, 4, 5, 116, 117, 118, 119, 120, 121, 122, 123, 124, 125, 126, 127, 128, 129, 130, 131, 132, 133, 134, 135, 136, 137, 138, 139, 140, 141, 142, 143, & 147 af ter placement of Pour N .

, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.

I l

l 5 Pour Location 2-010-038 Containment 2 Dome El 349' 6-1/2" to 356' 5-5/8" 2X2-001A002, Rev. 11 No violations or deviations were identifie . Containment (Steel Structures and Supports) - Units 1 & 2 (48053C)

Periodic inspections were conducted to observe containment steel and support installation activities in progress, to verify the following:

-

Components were being properly handled (included bending or straightening).

-

Specified clearances were being maintaine Edge finishes and hole sizes were within tolerance Control, marking, protection and segregation were maintained during storag Fit-up/ alignment meets the tolerances in the specifications and drawing No violations or deviations were identifie . Safety-Related Structures (Structural Steel and Supports) - Units 1 & 2 (48063C)

Periodic inspections were conducted to observe construction activities of safety-related structures / equipment supports for major equipment outside the containment to verify that:

-

Materials and components were being properly handled to prevent damag Fit-up/ alignment were within tolerances in specifications and drawing

-

requirement Specified clearances from adjacent components were being me No violations or deviations were identifie . Fire Prevention / Protection - Units 1 & 2 (42051C)

The inspector observed fire prevention / protection measures throughout the inspection perio Proper housekeeping measures to limit the amount of combustible materials and proper storage requirements are being maintaine Welders are using a welding permit with a fire watch and extinguisher. Post indicator valves are being maintained in the open position. Fire fighting equipment is in its designated areas throughout the plant.

' . _ _ _ _ _ . . _ _ _ J

_ ;

No violations or deviations were identifie . Reactor Vessel Protection - Unit 2 (50053C)

The inspection consisted of examination of the Unit 2 Reactor Vessel installed in containment to determine that proper storage protection practices were in place and that entry of foreign objects and debris was prevented. The inspector noted that protective covers were installed on the bottom mounted instrumentation penetration No violations or deviations were identifie . Reactor Vessel Integrated Head Package - Unit 1 (50053C)

The inspection consisted of examination of the Unit 1 integrated head package stored on the refueling floor in its designated laydown area to determine that proper storage protection practices were in place, entry of foreign objects and debris was prevented, and that access was controlle No violations or deviations were identifie . Reactor Vessel Internals - Unit 1 (50063C)

Periodic inspections were conducted during the inspection period when the upper and lower internals were stored in the cavity in their designated storage area to determine that proper storage protection practices were in place, entry of foreign objects and debris was prevented and that access was controlle l No violations or deviations were identifie . Safety Related Components - Units 1 & 2 (50073C)

The inspection consisted of plant tour; to observe protection of installed components to determine that adequate protection from dirt, dust, debris, water, or adjacent construction activities were in place. Unit 1 equipment examined included:

-

Residual Heat Removal (RHR) Pumps

-

Diesel Generators

-

Boric Acid Storage Tank

-

Containment Spray (CS) Pumps

-

Containment Penetration Encapsulation Vessel for Train A&B RHR and CS

-

Auxiliary Feed Pumps

-

Pressurizer l

-

Main Coolant Pump Casings

-

Steam Generators

-

Safety Injection Pumps

-

Auxiliary Component Cooling Water ( ACCW) Heat Exchangers

-

Component Cooling Water Heat Exchangers

-

-

-

ACCW Pumps

-

Reactor Makeup Pumps

-

Boron Injection Tank

-

Cable Spreading Room Train A and B

-

Integrated Reactor Pressure Vessel Head

-

4160V Train A and B Switchgear (IAA02 and IBA03)

-

13.8KV Reactor Coolant Pump Switchgear

-

Reactor Vessel Lower Internals

-

Reactor Vessel Upper Internals Unit 2 Equipment Examined Included:

-

Residual Heat Removal (RHR) Pumps

-

Containment Spray (CS) Pumps

-

Containment Penetration Encapsulation Vessel for Train A&B RHR and CS

-

Pressurizer

-

Steam Generators

-

Safety Injection Pumps

-

Reactor Vessel No violations or deviations were identifie . Electrical (Components and Systems) - Units 1 & 2 (51053C)

Periodic inspections were conducted during the inspection period to observe safety-related electrical equipment to verify that the installation and storage were accomplished in accordance with applicable requirements. The i following areas were examined at during the inspections:

-

Location and alignment

-

Type and size of anchor bolts

-

Identification

-

Segregation and identification of nonconforming items

-

Equipment space heating

-

Rotation of motor shafts

-

Lubrication and fluid levels

-

Protective coatings, preservations, dessicants, inert gas blanket, et No violations or deviations were identifie . Electrical (Cables and Terminations) - Unit I (51063C)

Periodic inspections were conducted during the inspection period to determine whether the raceway installation and protection of installed cable is in accordance with applicable codes, standards, and NRC Regulatory Guide r

In reference to the raceway installation, the following areas were inspected to verify compliance with the applicable requirements

-

Identification

-

Alignment

-

Bushings (Conduit)

-

Grounding

-

Supports and Anchorages In reference to the installed cable, the following areas were inspected to verify compliance with the applicabla requirements:

-

Protection from adjacent construction activities (welding, etc.)

-

Coiled cable ends properly secured

-

Unterminated cable ends taped

-

Cable trays, junction boxes, etc., reasonably free of debris

-

Conduit capped, if no cable installed

-

Cable supported No violations or deviations were identifie . Reactor Coolant Pressure Boundary (Welding) - Unit 2 (55073C)

Periodic inspections were conducted on Reactor Coolant System Primary Loop pipe welds at various stages of weld completion. The purpose of the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and (QC)

procedures were being met as follows:

-

Work was conducted in accordance with a process sheet which identifies the weld and its location by system, references procedures or instructions, and provides for production and QC signoff Welding procedures, detailed drawings and instructions, were readily

-

available and technically adequate for the welds being made.

i -

Welding procedure specification (WPS) were in accordance with the applicable ASME Code requirements and that a Procedure Qualification Record (PQR) is referenced and exists for the type of weld being mad I

-

That the base metals, welding filler materials, fluxes, gases, and insert materials were of the specified type and grade, have been properly inspected, tested and were traceable to test reports or certification That the purge and/or shielding gas flow and composition were as specified in the welding procedure specification and that protection was provided to shield the welding operation from adverse environmental condition ,,_

- _ _ -

*-

l 9 l

!

!

-

That the weld joint geometry including pipe wall thickness was specified and that surfaces to be welded have been prepared, cleaned and inspected in accordance with applicable procedures or instruction That the pipe to be welded to the component was assembled and held in place within specified gap and alignment tolerances allowed by the ASME Cod That a sufficient number of adequately qualified QA and QC inspection personnel were present at the work site, commensurate with the work in progres That disbursement of welding materials was controlled in accordance with approved procedure No violations or deviations were identifie . Safety Related Piping (Welding) - Unit 1 (55083C)

Periodic inspections were conducted on safety-related pipe welding at various stages of weld completio The purpose of the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:

-

that pipe alignment and fit-up tolerances were within specified unit That weld filler material being used was in accordance with welding <

specifications, that unused filler material was separated from other types of material and was stored in heated cans, and stubs properly removed from the work locatio That there were no evident signs of cracks, excessive heat input, sugaring, or excessive crow ,

Installation Activities During the inspection period, welds at various stages were observed in the following systems:

- Residual Heat Removal System

- Component Cooling Water System

-

Chemical & Volume Control System

- Nuclear Service Cooling Water System No violations or deviations were identifie ..

18. IE Bulletin, Confi rmatory Action Letter, and General Letter Followup ;

(92703B)

(Closed) IEB No. 83-05: "ASME Nuclear Code Pumps and Spare Parts -

Manufactured by the Hayward-Tyler Pump Company, Units I and The licensee was not required to respond to this bulletin since there are no '

safety related ASME code pumps or spare parts manufactured by Hayward Tyler Pump Company being used in plant Vogtle. A review was conducted of Bechtel Power Corporation Letter Log No. BG21186, File No. X7BC24, Dated 8/4/83 and Bechtel Power Corporation Letter Log No. BG30220, File No. X7BC24, dated 8/30/83 which referenced Westinghouse Electric Corporation Letter S.O. N GAE - 205/4704 Ref: BW - 4055, dated 8/16/83 which confirmed to the licensee that neitner Bechtel nor Westinghouse specified the use of Hayward Tyler Pump Company pumps or spare parts in any safety related application at plant Vogtl . IE Bulletins Sent for Information and IE Information Notice Followup (92717)

An inspection was conducted to determine whether the following procedural actions were taken by the licensee or construction permit holder for IE Information Notices: The Information Notices are received by managemen A review for applicability is being performe The Information Notices are distributed to the appropriate personnel at the corporate and site level For Information Notices applicable to the facility, appropriate corrective actions have been taken or are scheduled to be take A review of the licensee action on the following IE Notices was conducted:

IE Information Notice N Description Status 85-25 Consideration of thermal Open-awaiting conditions in the design engineer and installation of respons supports for Diesel Generator Silencer ~

85-19 Alleged falsification of Open-awaiting certifications and procurement alteration of markings response on piping, valves, and fitting Nonconforming structural Open-awaiting steel for safety-related procurement, us ]

-

..

.

In order to follow up the licensee's corrective actions and schedules the following IFI was identified: 50-424/85-26-02 and 50-425/85-25-02 " Review Licensee Action on Information Notice No's. 85-15, 85-19, and 85-25".

20. Participation in ACRS Meeting - Units 1 & 2 (94700)

On July 18 and 19, 1985, the ACRS subcommittee held a meeting in Augusta, GA pursuant to the operating license review. Regional representation at this meeting was performed by W. F. Sanders, J. F. Rogge 4.nd M. V. Sinkul e

-