ML19249E485

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IE Insp Repts 50-416/78-08 & 50-417/78-08 on 780516-19.No Noncompliance Noted.Major Areas Inspected:Warehousing,Fire Protection,Storm Damage,Reactor Vessel Internals & Licensee Response to IE Bulletins
ML19249E485
Person / Time
Site: Grand Gulf  
Issue date: 06/09/1978
From: Brownlee V, Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19249E483 List:
References
50-416-78-08, 50-416-78-8, 50-417-78-08, 50-417-78-8, NUDOCS 7910010578
Download: ML19249E485 (11)


See also: IR 05000416/1978008

Text

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NUCLEAR REGULATORY COMMISSION

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Report Nos.: 50-416/78-08 and 50-417/78-08

Docket Nos.: 50-416 and 50-417

License Nos.:

CPPR-118 and CPPR-119

Categories:

A2, A2

Licensee: Mississippi Power and Light Company

P. O. Box 1640

Jackson, Mississippi 39205

Facility Name:

Grand Gulf Nuclear Station, Units 1 and 2

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Inspection at:

Grand Gulf, Mississippi

inspection conducted: May 16-19, 1978

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Inspectors:

V. L. Brownlee

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Reviewed by:

Date

A. R. Herdt, Chief

Projects Section

Reactor Construction and Engineering Support Branch

Inspection Summary

Inspection on May_16-19,1978 (Report Nos. 50 I~ ^ '78-08 and 50-417/78-08

Mid Term QA Inspection TUr

. and 2]; 10 CFR 21

-

Areas Inspected:

TUnits 1 and 27; IE Bulletins (Units 1 and 2,; concrete (Unit 2); storm

damage (Units 1 and 2); reactor vessel internals (Unit 1); warehousing

(Units 1 and 2); fire protection (Units 1 and 2).

The inspection involved

55 inspector-hours on site by two h7C inspectors.

Results: No items of noncompliance or deviations were disclosed.

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RII Rpt. Nos. 50-416/78-8

I-1

and 50-417/78-8

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DETAILS I

Prepared by:

-rownlee, Principal Inspector

ae

V. L.

Projects Section

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Reactor Construction and Engineering

Support Branch

Dates of Inspection:

ay

6-19, 1978

7h

Reviewed by:

A

i te

A. R. Herdt, Chief

Projects Section

Reactor Construction and Engineering

l

Support Branch

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1.

Persons Contacted

Mississippi Power and Ligh_t Company (MP&L)_

a.

  • T. E. Reaves, Jr., Manager of Quality Assurance (QA)
  • P. V. Sly, QA Field Supervisor

G. E. Osborn, Construction Supervisor

D. F. Mahoney, Mechanical QA Representative

J. C. Fuller, Piping QA Representative

b.

Contractor Organization

Bechtel Power Corporation (Bechtel)_

  • R. L. Scott, Project QA Manager

T. L. Lee, Lead Superintendent, Night Shift

  • D. W. Strohman, QA Engineer
  • J. L. Martin, QA Engineer

The inspector interviewed 16 other licensee or contractor employees

during the course of the inspection. They included records, QC,

warehousing, supervisors and labor personnel.

  • Denotes those present at the exit interview.

Licensee Action on Previous Insp.ection Findings,

2.

(Closed) 417/78-06-01 Failure to Follow Specification

for Velding of Containment Liner

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The letter has

MP&L filed the letter of response on May 1. , l'78.

been reviewed by the IE:II responsible engineers and is detennined

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.-(

R11 Rpt. Nos. 50-416/78-8

and 50-417/78-8

I-2

to be acceptable.

The inspector verified that the specification

has been changed to correct the discrepancy between the specification

and welding procedure.

3.

Unresalved Items

There were no new unresolved items identified as a result of this

inspection.

4.

Independent Inspection Effort

Organization Changes (MP&L)

a.

i

Mr. J. E. Wimberly, MP&L Construction Supervisor, has lef t the

zmployment of MP&L to accept employment with Gulf States

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Utilities at the River Bend project.

Mr. G. E. Osborne,

previous MP&L civil QA representative has replaced Mr. Wimberly.

b.

Contractor Changes

I

The contract with the heat and vent duct contractor, IRSAY,

Skokie, Illinois, has been cancelled. The contractor was

performing both safety and non-safety related work.

Records

from IRSAY were turned over to Bechtel QC records prior to

IRSAY leaving the site.

General Mechanical Contractors has

been contracted to complete the heat and vent duct work.

c.

General Site Inspection

The inspector walked through Unit I and 2 facilities observing

general storm damage to the main structures and support facilities.

Additionally the inspector observed concreting prepour and

placement activities relative to Unit 2 and walked through the

main warehouse.

Considerable discussion was held with MP&L

management relative to the project schedule.

5.

Partial Mid-

Term Construction Permit QA Inspection - Field Procurement

TUnits 1 and 2)

The inspector reviewed the on-site program for procurce nt of

structural support material.

Bechtel Specification Nos. 9645-C-

121.0, 9645-C-131.0, and 9645-C-151.0 are the specifications for

the furnishing of structural steel for category I structures;

miscellaneous and embedded steel and iron for Category I structures;

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and containment, drywell and suppression pool respectively.

Bechtel

Nuclear QA Manual Policy Nos. QGG-4.1 and QGG-7.1 defines home

office and field procurement policies and source evaluation and

selection policies.

Bechtel Work Plan Procedure WP/P-9 instructs

the field engineer on how to initiate the field material requisition

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RI-I Rpt. Nos. 50-416/78-8

and 50-417/78-8

I-3

forms.

Bechtel QA Instruction No. 4.1-1 instructs the project QC

Group on how to review and approve the field material requisitions.

The Field Procurement Individiual Jobsite Instructions describe how

field procurement performs their functions. The procurement depart-

ment utilizes an approved venders list for selection of bidders.

The inspector selected purchase order Nos. 9645-F-25346 and 9645-F-

25714, for structural materials, to determine whether the QA canual

procedures were implemented, whether the specification requirements

were imposed, whether supplier documentation was required, whether

the supplier was prequalified, and that the field QC records contained

the required documents.

The material requisitions were in order

and properly reviewed and signed off; the purchase orders referenced

!

the applicable specification, materials, tests reports, part 21 and

documentation requirements; the field QC records contained the

Material Receiving Instruction and Inspection Record, Material

Receiving Report, Documentation Requirement Forms, Material Test

Reports and purchase orders,

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No items of noncompliance or deviations were identified.

6.

10 CFR 21 Inspection

The inspector selected Purchase Order Nos. 9645-M205.1, Rev. 21;

9645-M-257.0, Rev. 16; 9645-C-121.0, Rev. 35; 9645-M-062.0, Rev. 9;

9645-M-300.0, Rev. 21; F-25346; and F-25918 to verify that purchase

documents initiated at Gaithersburg and at the site were including

the Part 21 clause. The inspector confirmed that all purchase

orders did include the part 21 clause.

Additionally the inspector verified that three on site subcontractors

were complying with the posting requirements of Part 21.

During the period of the inspection the licensee discovered that

Bechtel subcontracting had failed to impose Part 21 requirements on

a subcontractor, General Mechanical Contractors (See Paragraph 4.b

above). This matter was quickly corrected by amending the contract

to impose Part 21 requirements.

No items of noncompliance or deviation were identified.

7.

(Closed) IEB 77-08 - Assurance of_ Safety _and Safeguards During

an Emergency - Locking Systems (Units 1 and 2)

_

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MP&L letter of March 16, 1978, reports that MP&L has concluded

their review and that the design of the facility together with the

emergency and security plan will adequately meet the criteria set

forth in the bulletin.

IE:II has no further questions regarding

this matter.

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R11 Rpt. Nos. 50-416/78-8

and 50-417/78-8

I-4

8.

(Closed) IEB 78-02 - Terminal Block Qualification (Units 1 and 2)

MP&L letter of March 9, 1978, reports that no such unprotected

terminal blocks will be used in the described service. MP&L plans

to protect all such terminal blocks by enclosing them in boxes

which meet or exceed NEMA Type 12 requirements.

IE:II has no

further questions regarding this matter.

9.

Licensee Identified Item

Small Fire - Reactor Vessel Pedestal Area (Unit 1)

!

On April 4, 1978 MP&L notified IE:II of the occurrence of a small

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fire which had developed underneath Unit I reactor vessel. The

fire was determined to have been caused by an electrical short in

110 volt extension trouble light. The short ignited some plastic

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covers and burlap which burned for less than two minutes. The fire

extinguished with a dry chemical type extinguisher.

The reactor

vessel bottom head was filled with black soot and powder from the

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extinguisher was adhering to the inside of the vessel skirt and the

Leue; of the vessel.

Ash and powder fell to the control red drive

piping work platform and on the insert withdraw lines.

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The inspector reviewed the Bechtel Safety Department Fire Report;

the Bechtel, Reactor Controls Incorporated; General Electric I&SE

nonconformate reports; and the General Electric hTD engineering

evaluation and cleanup instructions. MP&L and their contractors

have concluded that there was no damage to safety related equipment.

This matter is thoroughly documented in on-site records and appears

to have received adequa e attention.

IE:II has no further questions

regarding this matter.

10.

Management Interview

The inspector met with the licensee representatives (denoted in

paragraph 1) at the conclusion of the inspection on May 19, 1978.

The inspector summarized the scope of the inspection as follows:

Licensee action on previous inspection findings; independent inspec-

tion effort; mid-term QA; IE Bulletins; 10 CFR 21; and licensee

identified items.

No items of noncompliance were identified.

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't

RII Rpt. No. 50-416/78-08

and 50-417/78-08

11-1

[!O/9

W. B. Swan,[ Civil Engineer

,

Date

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DETAILS II

Prepared by:

,

Engineering Support Section No. 1

Reactor Construction and Engineering

Support Branch

Dates of Inspection: May 16-19, 1978

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Reviewed by:_

C. Bryahf, Chief

Date

..ngineering Support Section No. 1

Reactor Construction and Engineering

Support Branch

i

1.

Persons Contacted

Mississipy_i Pcver and Light Companj- (MP&L)

a.

T. E. Reaves, Jr., Manager, Quality Assurance (QA)

i

G. E. Osborn,

Nuclear Construction Supervisor

  • P. W. Sly, Quality Assurance Field Supervisor

D. F. Mahoney, QA Repres :ntative, Mechanical

S. F. Tanner, QA Represei tative, Welding and NDE

J. C. Fuller, QA Representative, Piping

b.

Contractor OrEanizations

(1)

Bechtel Power Corporation _(Bechtel)

_

R. L. Scott, Project QA Manager

  • D. W. Strohman, Quality Assurance Engineer

T. L. Lee, Construction Superintendent, Second Chift

  • J. L. Martin, QA Engineer, Civil

R. Ingraham, Froject Safety Supervisor

(2)

General Electric Cogany__ Installation and Services

Engineering _ Division (16SE)

D. Orr, We ding Supervisor

  • Denotes those present at the exit interview.

2.

Licensee Action on Previous Inspection Findings

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This area was not inspected.

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RII Rpt. Nos. 50-416/78-08

- and 50-417/78-08

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3.

Unresolved Items

Unresolved items are matter about wh?ch more information is required

in order to ascertain whether they are acceptable items, items of

noncompliance, or deviations.

An unresolved item disclosed during

the inspection is discussed in Paragraph 4.

4.

Independent _ Inspection Effort

a.

Warehouse:

During a backshift inspection, the Bechtel receiving warehouse

on site vas inspected. As an added precaution, metal cabinets

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housing c >ntainers of flammables have been moved outside the

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warehouse.

This prevents the possibility of fires near stored

Class I materials and equipment caused by inadvertancies such

as piercing a cabinet with fork lift prongs.

b.

Concrete Placement:

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The inspectors observed a night shift placement of a portion

of a 2,700 cubic yards section of the foundatica cat of the

Unit 2 auxiliary building under WP61R Q2 T-21-W-21093 using

CC2 mix.

For each 50 yards, sampling was done et the mixer

discharge site into the trucks. For each 500 cubic yards,

samples were taken at a pump line discharge.

In review of the concrete mixer report, test data and the QC-

2C Supplement Report for pump line discharge sample test data,

the inspector noted some apparent improbabilities.

The four

samples taken had a recorded slump of 2 1/2 inches although

the same mixes sampled at the mixer had variable slumps.

Also, the recorded air entrainment percentages recorded show a

reducing differential, or drop, in slump as the pipelines were

shortened, an actual rise for one case (4.5% at the mixer,

2.8% at the truck discharge and a rise to 3.7% at the end of

the pump line.) The inspector challenged these aberrations.

MP&L QA had Bechtel QA mnd QC engineers review the data and

confer with Pittsburg test laboratories.

PTL maintained that

the test data had been recorded correctly.

This indicated

that perhaps the instructions for recording slump measurements

at the pump line end may have been misunderstood by the technician

and the air entrainment measurement devices might be out of

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calibration or the measuring technique not followed correctly

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Nos. 50-416/78-0S

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RII Rpt.

11-3

and 50-417/78-08

the

The licensee was told that

at one or the other locations.

417/78-08-01,

matter would be left as an unresolved item,

requiring recalibration of the air entrainment meters, PTL

review of techniques for air measurement and measuring and

specifica-

recording slumps, and licensee review of the latest

be

tion revisions to determine that slump of concrete to

conveyed by Cretercrane is adequately controlled.

Batch Plant Operations _:

c.

The inspectors observed batching and sample taking and testing.

1_:

Reactor Vessel Internals Installation, Unit

d.

The inspector entered the reactor vessel dur!ng

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installed brackets, supports, in process diffusers, and one

Access and

installed diffuser and its rams head sections.

cleanliness controls to the vessel were being imposed.

In the four areas inspected, no noncompliances with quality

In the concrete area one

recuit tnents were identified.

unresolved item was developed.

Inspection of Status of Tornado Damage Corrections

5.

Four creas were considered:

a.

Unit 1 hyperbolic cooling tower

structures

b.

Unit I containment and adjunct

MP6L permanent warehouse

c.

E-'.h Plant Control trailer

d.

I cooling tower area has been evacuated by the subcontractor,

The Unit I

The Unit

who has shifted to excavation for the Unit 2 tower. insurance

tower area has been isolated by tape barriers pending

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the

claic settlements and an engineering study and evaluation t at

damaged tower can be repaired to an insurable condition.

Tornado damaged construction equipment and scattered materials have

and adjacent areas.

Tecporary

been removed from the containmentunscheduled openings in sidings.

closures had been crected at

Cosmetic repairs to concrete and replacement with regular

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sheathing had not been started.

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Rll Rpt. Nos. 50-416/78-08

and 50-417/78-08

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Dented and torn liner in the dome transition zone of the

containment has been delineated but CB&I has not been released

to start repairs.

The licensee stated that a settlement had been reached with

the insurer and work is proceeding normally in the basic plant

areas.

Wall paneling sections had been destroyed in both ends of the

MP&L warehouse. Temporary closures have been erected for

weather protection and waterials of high value have been

secured in the Category I storage room.

The batch plant

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control trailer and control equipment had been rcplaced by

those from the back up batch plant and had been recertified.

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The uniformity of a batch from the recctivated plant has been

verified by test.

6.

Procedures - Fire Prevention / Protection

The licensee's com=itments on facilities to be provided for fire

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prevention, suppression and urotection were published in PSAR

section 3, Criterion 3 - Fi e Protection and section 9.5.1 Fire

Protec_ tion System. Additional criteria are set out in the construction

specifications and drawings.

Additional criteria and guidance are available in proposed Regulatory

Guide 1.120, Fire Protection Guidelines for Nuclear Power Flants

(out for comment until November 1978) and the NPPH, ANSI, ASTM,

IEEE, MAERP-NELPIA, and U.S. NRC regulatory guides and other Commission

documents listed in the Reference to R.G.

1.120.

The licensee is implementing, as the status of construction permits,

the requirements and guidance of the controlling criteria and

guidance through Bechtel WP&IR No. NSA 13-2-00000-Y01, Revision 3.1

dated July 7, 1977, " Procedure for Controlling and Extinguishing a

Fire on Grand Gulf Construction Site"; by supplemental field instructions,

written and verbal; by periodic scheduled training of fire brigade

personnel and by weekly inspections of fire extinguishers, hydrants,

loop line and installed sprinkler systems; housekeeping; and by a

fire permit system.

The inspector reviewed the WP&IR and the supplemental documents and

discussed them in detail with the Bechtel Project Safety Supervisor.

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The installed permanent fire protection systems were inspected.

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RII Rpt. Nos. 50-416/78-08

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and 50-417/78-08

From the document review, inspection of hardware and discussions

with responsible personnel, the inspector determined that adequate

protection can be provided during the construction phase up to

start of Unit 1 fuel loading.

to .ontrol

Adequate and approved fire prevention procedures exist

the following during const! uction activities:

Storage, handling, and use of flarnable caterials.

a.

Storage, centrol, and use of combustible materials relative to

b.

locations of flar.mable materials and ignition sources.

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Use and control of open flames and other Ignition so rces

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c.

which may be used in areas containing flammable materials.

Adequate and approved procedures exist relative to fire suppression

during construction activities which use ignition sources and/or

flammable materials, including:

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a.

Use, testing, naintenance, and identification of fire suppicssion

equipment.

Use, testing, maintenance, and identification of related

b.

auxiliary equipment.

Approved procedures exist relative to fire fighting activities

in the areas of:

Supervision / control

a.

b.

Action plan

c.

Communications

Approved procedures exist relative to training in the areas of

fire prevention, protection, and suppression; and training has

been conducted as specified,

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RII Pipt. Nos. 50-416/78-08

and 50-417/78-08

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Adequate and approved procedures exist for the control nf the

procedures identified in items 1 through 4, in the areas of:

a.

Revision

b.

Approval

c.

Distribution

In the areas axamined no nonconpliance with requirements was

identified.

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7.

Management Interview

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An exit interview was held with Mr. P. Sly, Quality Assurance Field

Supervisor and representatives of the MP6L and Bechtel staffs.

Inspection scope and findings were discussed in the areas of tornado

damage correction, concrete, warehousing, reactor vessel internals

and project fire protection.

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The inspector stated that an unrecolved itom in the area of concrete

had been identified, U.R.I. 417/78-08-01, as described in section 4

of these Details,

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