ML17055C051

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Insp Rept 50-220/86-10 on 860616-20.Violation Noted:Placing Hydrogen Water Chemistry Sampling Line in Svc Prior to Performing Hydrostatic Pressure Test
ML17055C051
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 07/09/1986
From: Mcbrearty R, Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17055C049 List:
References
50-220-86-10, NUDOCS 8607220343
Download: ML17055C051 (10)


See also: IR 05000220/1986010

Text

U.S.

NUCLEAR REGULATORY COMMISSION

REGION I

Report

No.

50-220/86-10

Docket

No.

50-220

License

No.

DPR-63

Category

C

Licensee:

Nia ara

Mohawk Power

Cor oration

300 Erie Boulevard West

S racuse

New York

13202

Facility Name:

Nine Mile Point Unit

1

Inspection At:

Scriba

New York

Inspection

Conducted:

June

16-20

1986

Inspectors:

R

A.

cBr

ty,

R

ctor Engineer

date

Approved by:

J.. Wiggi

Chief, Material s and

Processes

Section,

EB,

DRS

date

Ins ection Summar:

Ins ection

on June

16-20

1986

Re ort No. 50-220/86-10

~A" I: I,

AI

inspector of Control

Rod Drive Stub Tube examinations,

Data review regarding

Recirculation

System

and

Emergency

Condenser

piping and activities related to

the Hydrogen Water Chemistry Sampling Line hydrostatic

pressure

test.

Results:

One violation was identified:

placing the Hydrogen Water Chemistry

Sampling Line in service prior to performing the hydrostatic

pressure

test.

8b07220343

8b0711

PDR

ADOCK 05000220

8

PDR

r

0

DETAILS

1.

Persons

Contacted

Nia ara

Mohawk Power

Cor oration

  • J. Boyler, Engineer

"T. Breigle, Quality Assurance

Engineer

  • W. Connolly, Quality Assurance

Program Manager

  • W. Drews, Technical

Superintendent

~f. Hawksley, ISI

  • H. Master III, Quality Assurance

Engineer

  • P. Mazzaferro, Assistant Supervisor-Technical

Support

  • T. Perkins,

General

Superintendent

~R. Randall,

Supervisor-Technical

Support

  • T. Roman, Station Superintendent
  • G. Snyder,

Associate

Generation

Engineer

  • B. Wolken, Engineer

T. White, Assistant

Generation Specialist

Chica

o Brid e and Iron

C. Kirk, Welding Quality Assurance

Superintendent

United States

Re ulator

Commission

  • W. Cook, Senior Resident

Inspector

~Denotes

those present at the exit meeting.

2.

H dro en Water Chemistr

S stem

H drostatic

Pressure

Test

The Hydrogen Water Chemistry

System modification involved the installation

of a sampling line from a perforated

LPRM tube through

an already existing

containment penetration.

The modification was to be done in accordance

with the rules'of the

1980 edition of ASME Section III, Subsection

NC with

the

Summer

1982 Addenda.

Welding was to be controlled by ASME Section

IX,

1980 edition through

Summer

1982 Addenda.

The inspector

reviewed the following to ascertain

compliance with the

applicable

requirements

of ASME Section III, Subsection

NC:

Niagara

Mohawk Design Transmittal

NlY85M9271 LF

Niagara

Mohawk Procedure

No. Nl-ISI-HYD-94

CBEI Procedure

SI-11,

Rev.

1

CB&I Traveler RSL-1, Contract

No. 863060/64

The inspector

found that the controlling documents

did not clearly define

the

sequence

in which work on the

system

was to be accomplished

with re-

spect to the Code-required

hydrostatic pressure

testing.

Construction

and

testing requirements,

in some cases,

were delineated

in narrative

form in

both the licensee's

and contractor's

procedures

and were then incorporated

in the

CBE I Traveler which governed

the field work.

The Traveler

was

found to permit system hydrostatic tests .to occur prior to

a final welding

operation

between

the containment penetration

and the sampling

system

piping.

This resulted

in the

system being placed in operation before the

completed

system

was hydrostatic

pressure

tested

as required

by ASNE

Section III. Also, as

a result of the incorrect

sequence

provided by the

Traveler,

a pin hole leak developed

in the system piping at the reactor

building side of the containment

penetration

which was not detected until

the plant was in a startup

mode

and pressurized.

The fact that

an inadequate field installation procedure

was

used for

this modification is

a violation of the applicable

ASME Section III

requirements.

(220/86-10-01)

3.

Control

Rod Drive

CRD

Stub Tube Examination

The inspector

reviewed documents,

interviewed licensee

personnel,

and

examined nondestructive

examination

records

associated

with CRD Stub Tube

c) acking.

The following were included in the inspector '

review:

Stub Tube/Control

Rod Drive Penetration

Repair Program

Inspection

Plans for Spring

1986 Refueling Outage

Procedure

No. 6284-ISI-082,

Revision

1, "Ultrasonic Examination

Procedure

For Reactor

Vessel

Control

Rod Drive Housings

From the

I.D."

Procedure

No. 00000-ISI-029,

Revision 5, "Generic Manual Ultrasonic

Examination Procedure"

Nondestructive

Examination

Data associated

with CRD 30-07,

30-47,

34-07

and 46-27.

The above review was

done to ascertain

compliance with licensee

commit-

ments

and to verify that the examinations

were done

by qualified person-

nel .

The inspector

found that

CRD Housing leaks

were repaired

by a rolling

technique

which had previously been

used to make repairs.

The affected

components

were ultrasonically examined before

and after the rolling

operation

by qualified technicians

using approved

procedures.

The li-

censee

had committed to ultrasonically

examine at least

one previously

rolled housing during each refueling outage.

The examination of CRD 46-27

fulfilled that commitment.

The inspector

found that licensee

commitments

were met and that required

examinations

were completed.

No violatibns were identified.

4.

Preservice

Ins ection

PSI

Data

Review

During 1986 refueling outage,

the licensee

replaced

emergency

condenser

piping and performed Induction Heat Stress

Improvement

( IHSI) on 26 welds

in the recirculation

system.

The inspector

reviewed the

1986 Outage

PSI Plan

For Replaced

Piping and

Components

at Nine Mile Point Unit

1 - Document

No. 81A1030,

Revision 0.

This Plan delineated

the

PSI requirements

and provided appropriate

diagrams

to identify the areas for examination of those

Class

1,

2 and

3 portions

of piping and components

which were replaced

or given IHSI during the

outage.

The examinations

were intended to meet the

ASME Code Section XI,

1980 Edition through Winter 1981 Addenda.

In addition,

selected

weld

examination

data were reviewed to ascertain

that program requirements,

code requirements

and regulatory requirements

were met.

The following

were included in the inspector's

review:

32-FW-12S-5,

Recirculation

System

28" diameter valve to pipe weld

32-FW-12S-2,

Recirculation

System

28" diameter

elbow to pipe weld

39-FW-4043-09,

Emergency

Condenser

10" diameter

safe-end

to pipe weld

39-SW-4043-019,

Emergency

Condenser

10" x 12" reducer to pipe weld

The recirculation

system ultrasonic examinations

were

done using

UDRPS

automated

techniques,

and the emergency

condenser

welds were

examined

with manual

techniques.

Additionally, the welds were liquid penetrant

examined

per Section

XI requirements.

The inspector

found that applicable

code

and regulatory requirements

were

met,

the examination results

were properly documented,

and the examina-

tions were done

by qualified personnel

using approved

procedures.

5.

Personnel

uglification/Certification Records

Certification records

were reviewed for personnel

who were associated

with

the

NDE performed

on the welds listed in paragraph

4.

This included the

automated

examinations

performed

on the recirculation

system welds.

The

review was

done to ascertain

that the individuals were properly qualified

to perform their assigned

duties.

e

The records

indicated that the examiners

were qualified in accordance

with SNT-TC-1A and the Nuclear

Energy Services qualification program.

I

The individual who analyzed

the

UDRPS automated

data

was certified to UT

Level II limited to automated

techniques

and

had received

EPRI training

in IGSCC planar flaw sizing,

and in the examination of weld overlays.

He

had successfully

passed

the practical

examinations,

given at the

EPRI

NDE

Center,

in flaw sizing and

IGSCC detection

data acquisition

and analysis

using the

UDRPS system.

His activities at Nine Nile Point Unit

1 were

limited to the analysis of data collected

by

UDRPS during the examination

of recirculation

system welds.

No violations were identified.

ualit

Assurance/ ualit

Control Interface

In connection with the review of the procedures

used to control the

installation of the hydrogen

sampling modification discussed

in paragraph

2, above,

the inspector

noted contractor

QC hold points established

in

the Traveler.

The inspector

thus concluded that

CBAI QC had reviewed the

Traveler

so that appropriate

hold points could be established.

The in-

spector also noted that, despite this

QC review, the inadequacy

of the

Traveler with regards

to the sequencing

of hydrostatic testing

and work

activities was not identified.

7.

Exit Interview

The inspector

met with licensee

representatives

(denoted

in paragraph

1)

at the conclusion of the inspection

on June

20,

1986.

The inspector

summarized

the purpose

and the

scope of the inspection

and the findings.

At no time during this inspection

was written material

provided by the

inspector to the licensee.

1

4

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