ML16340B961

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IE Insp Repts 50-275/81-17 & 50-323/81-11 on 810622-26.No Noncompliance Noted.Major Areas Inspected:Licensee Action on Previous Insp findings,10CFR50.55(e) Items & IE Bulletins & Circulars
ML16340B961
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 07/22/1981
From: Bishop T, Burdoin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML16340B962 List:
References
50-275-81-17, 50-323-81-11, IEB-79-13, IEB-80-05, IEB-80-5, IEC-80-04, IEC-80-09, IEC-80-10, IEC-80-23, IEC-80-4, IEC-80-9, IEC-81-08, IEC-81-8, NUDOCS 8108180451
Download: ML16340B961 (12)


See also: IR 05000275/1981017

Text

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50-275/81-17

Report

No.

U. S.

NUCLEAR REGULATORY COMMISSION

OFFICE

OF INSPECTION AND ENFORCEMENT

REGION V

Docket No.

Licensee:

P.

0.

Box 7442

License

No.

p

PR-69

Safeguards

Group

F

n i co

Calif rnia

94106

Facility Name:

Di bio

C n on

U its'.

Inspection at:

D abl

an

on Site

San Luis Obis

o Count

California

8 Cor orate Office

Inspection conducted: June

22-26

1981

Inspectors:

lh- l

J.

F. Burdoin, React

Inspector

y/Zz/Pl

Date Signed

Approved by:

T.

W. Bisho

Chi

Pro ects Section

1

Reactor Construction Projects

Branch

Date

S gne

7/>z/Sl

Date

S gne

Summary:

Ins ection durin

eriod of June

22-26

1981

Re ort No. 50-275 81-17. and

0-323 81-11

~Ad:

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of construction

and modification activities including:

licensee action

on previous inspection findings, 50.55(e)

items

and

IE Bulletins and Circulars.

The inspection involved 34 inspector

hours

by one

NRC inspector.

Results:

No items of noncompliance

or deviations

were identified.

8108180451

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DETAILS

1.

Individuals Contacted

a ~

Pacific

Gas

and Electric

Com an

PGSE

J.

B. Hoch, Nuclear Projects

Engineer

R.

D. Etzler, Project Superintendent

  • M. N. Norem, Resident Startup

Engineer

B.

C.

Lew, Nuclear Plant Operations

R.

C. Thornberry, Plant Manager',

W.

B. Kaefer, Tech.: Assist to Plant;Manager

R.

C.

Howe, Senior Nuclear Generation

Engineer

  • F; M. Russell; Acting,'Resident Civil Engineer

D.'. Rockwell, Resident Electrical

Engineer

J., g., Aranon,

Resident'- Mechanical

Enginee'r

  • R. T.'widdy, gA Supervisor
  • S: J.'oat,

Lead

gC Engi'neer

K. A.'lee,

gC Engineer

  • R. W.'aylor, gA Engineer
  • I. L, MacDonald, Acting Resident Electrical

Engineer

Various other Engineering

and

gC personnel.

  • Denotes attendees

at June

26,

1981 Exit Meeting.

2.

Plant Tour

Upon arrival at the site the inspector toured the Diablo Canyon Units

1 and

2 to observe

completed work.

Specific areas

examined included

Unit 1 vital switchgear

and onsite

power systems,

the

ECCS systems,

the control

room and the containment;

and Unit 2 containment.

No items of noncompliance or deviations

were identified.

3.

Licensee

Action on 50.55

e

Items

a.

0 en for Unit 2

Deficient Low Level

Am lifiers in the Reactor

Protection

S stem

The licensee

submitted

a final 50.55(e) report, dated

March 9,

1981, regarding defective operation of Hagan

Model

118 low level

amplifiers used in the reactor protection system.

The resolution

of the problem was to replace all 2N699 transistors

in the gl4

location of each

module with 2N4383

(Sprague

TP4384) transistors.

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The inspector determined,

from discussions

with licensee that

all of the replacement transistors

have not been received

on site

to modify Unit 2 amplifiers.

It was also learned that these

modifications in the amplifier modules will be accomplished

concurrent

with maintenance

replacement of electrolitic capacitors

in the

Hagan amplifiers in late

1981 or early 1982.

(Closed for Units

1 and

2

Se aration of Neutral

Block from Neutral

Bus in

1 0

VAC Vital Instrument

Power Panels

The licensee

reported

by telecon

on May 14,

1981 that the neutral

terminal block became

separated

from the panel

ground

bus in

the

120

VAC vital instrument

power panel

no.

PY13 for Unit l.

Once separated

the

120

VAC circuits in this panel

were open-circuited

causing the devices

powered from this panel to become deenergized.

A preliminary written report was submitted

on June

12,

1981.

The licensee

proposed to replace the neutral

blocks in all eight

(four per unit)

120

VAC vital power panels with neutral

blocks

of an improved design.

The installation of the new neutral

blocks

in the seven of the eight vital 120

VAC power panels

was completed

June

24,

1981.

Completion of the eighth unit in panel

PY24 (Unit 2)

is awaiting delivery of standoff insulators.

The inspector

examined

the design for the

new neutral

blocks

and verified that seismic

review and design verification had been accomplished.

The 120

VAC vital power panels

were inspected

following installation

of the neutral

blocks to ensure

the work was completed.

This item is closed for Units

1 and

2 upon receipt

and examination

of licensee's

final written report.

(0 en for Units

1 and

2

Deficienc

in Containment

S ra

Pum

Startinq

The li'censee

submitted

a preliminary 50.55(e) report,

dated January

19,

1981, which concerns 'spray

pump start timing.

The concern

is the simul'taneous

starting of the,;containment

spray

pumps initiated

by high-high containment

pressure

(P)-'signal with other

ESF equipment

initiated by the safety injection (S) 'signal.

This could result

in the'ripping of an emergeiicy

bus

and the loss of ESF functions

following a

LOCA.

\\

The inspecto'r reviewed the present'tatus

of this issue with the

licensee.

'The issue is under re-evaluation

by the licensee's

engineering

department

and the

NSSS" manufacturer

(Westinghouse)

to determine the proper assumptions

and solutions.

'A solution/

conclusion for this issue will be forthcoming in the near future.

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Crackin

in Heav

Ru ture Restraints

Weldments

see

IE Ins ection

Re ort No. 50-275 50-323 81-04

e.

The inspector reviewed this issue for Unit 2 with the licensee.

The repair work (reported approximately

60Ã complete in March

1981)

has

been inactive.

However, recently the repair work of

fractured restraint weldments for Unit 2 was restarted

and is presently

going forward.

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0 en for Unit 2

Reduced

Ultimate Tensile Values for One-Inch

Hilti Ex ansson

Anchors

see

Ins ection

Re ort No. 50-275 81-10)

The inspector reviewed this issue for Unit 2 with the licensee.

The re-evaluation of pipe supports for large bore pipe (2', inch

diameter

and larger) is being conducted

by the licensee's

engineering

department

in,San Francisco while the re-evaluation of pipe supports

.

for small

bore pipe is being conducted

by the Field Engineering

Section at the Diablo Station.

4.

Licensee

Action on IE B'ulletins and Circulars

The following IE Bulletins and Circulars were reviewed

by the inspector

to determine the thoroug)ness of licensee

actions to correct or avoid

those

known or potential deficiencies:

1 '8

d

a.

(0 'en. for "Unit.2 -IE.,Bulletin 79'-13:

Crackin

in Feedwater

Pi in

b.

C.

~Sstem

Thee" inspe'ctor

r eviewed 4hi's bul:le'tih"with the licensee.

The

,"li'cen'see'isI co'mmÃted~to"csomplete<aii, jnspection

program following

h'o'er functus'onal'testing

tentati ve'ly 'scheduled

for December

1981.

(Clo'sed fo'.'Unit 2) IE',Bulletin'80-05:

Vacuum Condition

esu,

sng

sn

amage

o

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up.

an

s

Th'e:inspector exami'ned"theeinstall'ations

of the external

stiffen'ing rings

and the,,vacuum r'elief valves which adequately

< protects'"the

holdup tanks

'from'damage" due to vacuum conditions.

The installations

were found to be satisfactory.

Closed for Units'

'and

2

IE Circular 80-04:

Securing of

Threaded

Lockin "'Devices

on

Sa et -Re ate

u)pmen

The licensee

has demonstrated

to the inspector's

satisfaction

that the modifications to various pieces of equipment required

by the Circular have

been accomplished

at th'e Diablo Canyon

Station where applicable.

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". IE Girc'ular. 80-09: ",Problems with Plant

e.

Internal

Communicati'onS

stem

The inspector'ev'ieyed

this circular with the licensee

and

determined that additional, testing ofthe,effects of portable

radio transmission',on

c'on'trol'oom instr'umentation is still

going forward.,; -.-

0 en for..Units l..and

2

IE Curcular

80-'10:

Failure'to Naintain

Environmental

ual ificati on

The wrong class of insulating'material

had been

used in reconnecting

motor leads following maintenance

at the H.B. Robinson Nuclear

Plant.

The inspector reviewed this Circular with the licensee

and determined that the maintenance

procedure,

which will

monitor this issue

once the plant becomes

operational,

has

not been

completed at this time.

Closed for Units

1 and

2 'E Circular 80-23:

Potential

Defects

in Beloit Power

S stems

Emer enc

Generators

The licensee's

review of the electrical

equipment records

has

determined that no generators

manufactured

by Beloit Power

Systems

are used in Class

I application at Diablo Canyon Units

1

and 2.

g.

0 en for Units

1 and

2

IE Circular 81-08:

foundation Materials

Insufficient compaction of foundation

and backfill materials

during the construction of nuclear plants

has resulted in

excessive

settlement of plant structures

at

a number of sites.

The inspector reviewed this circular with the licensee.

It

has

been determined that the containments

and most of the

station buildings rest

on bedrock

and that only a limited

amount of backfill and compaction

was required in the area of

the station buildings.

There is

some backfill in the turbine

building area

and diesel

generator

areas.

Hajor backfilling

and compaction

was required in the

230 and

5QQ

KV switchyard

areas.

The compaction of backfill in the turbine area for Unit

1 was

accomplished with hand pneumatic

compactors.

Unit 2 construction

period was later and by that period backfilling in the turbine

area (Unit 2) was being accomplished with concrete

(2000 psi).

The instructions/specifications

for compaction

were reviewed

a1ong

with compaction records for the turbine building.

Compaction

tests

were made after each

6 to 8 inch liftof compacted backfill.

If compaction

was less

than

90%, the area

was

removed

and backfilled/

compacted with new material.

Bench marks inscribed at various locations

on the turbine building and monitored periodically during construction

did not indicate any appreciable

settlement "o5 .the=-bui'fding.

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In the switchyard areas,

the backfilling and compaction

was

accomplished

early in the construction period.

The area

was

monitored for settlement for approximately

two years after

backfilling was completed before

any construction

was

commenced

on the sites.

The compaction

procedures

and records for the

switchyard areas

were reviewed

and no deviations

were identified.

The inspector's

audit of records

on this issue is incomplete

at this time.

This item will remain open.

5.

Mana ement Interview

The inspector

met with licensee

representatives

(denoted in Section

1)

on June 26,

1981.

The scope of the inspection

and the inspector's

findings,

as noted in this report, were discussed.

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