ML16341E208

pCi/cc

1.15

E-2

4.58 E-4

NRC

pCi/cc

1.55

E-2

5.64

E-4

Ratio

DCPP/NRC

0. 74

0. 81

"Agreement

~Ran

e

0.75 - 1.33

0. 60 - 1.66

"See enclosure

for explanation.

The results

in Table

1 indicate marginal

agreement

for the waste

gas

category.

The

NRC calibration for the glass

bulb geometry,

however,

was

performed with a glass

bulb of slightly different capacity

and wall

thickness

than the bulb used to obtain this sample.

Given the

uncertainties

associated

with this measurement,

the agreement

is

adequate.

Table

2

Iodine Cartrid

e

Nuclide

I-132

I-133

I-135

BR-82

~WC1

ml

6.14 E-10

5.10 E-11

2.61 E-10

9.97

E-11

1.89

E-10

NRC

pMCi ml

5.04 E-10

2.44 E-ll

2.00 E-10

1.07 E-10

1.13 E-10

Ratio

DCPPGPNRC

1. 22

2 ~ 09

1. 31

0. 93

l. 67

Agreement

Rancae

0.75 - 1.33

0.40 - 2.50

0.60 - 1.66

0. 50

2. 00

0.60 - 1.66

Table

2 lists the results

obtained for the iodine cartridge

geometry.

Because

Diablo Canyon routinely uses silver zeolite for iodine

collection,

a silver zeolite cartridge rather than

a charcoal

cartridge

was

used for this test.

The low activities observed

in this sample

are

reflected

by the relatively wide agreement

range indicated in the table.

In general,

the agreement

is adequate.

Table

3

Li uid Waste

Nuclide

Co-58

Cs-134

OCPP

RCi/ml

8.54

E-7-

2.89

E-7

1.07

E-4

8.54

E-6

7. 52 E"6

1.50 E-6

1.81 E-6

NRC

RCi/ml

1.16 E-6

1.65

E-7

1.20 E-4

9.43

E-6

1. 30 E-5

1. 83 E-6

2. 33 E-6

Ratio

DCPP/NRC

0. 74

l. 75

0. 89

0. 91

0. 58

0. 82.

0. 78

Agreement

~Ran

e

0.60 - 1.66

0.40 - 2.50

0.80 - 1.25

0.75 - 1.33

0.60 - 1.66

0.60 - 1.66,

The results

for split samples

of chemical

drain tank liquid waste are

summarized in Table 3.

Except for I-131, adequate

agreement

is indica+,ed

for all other nuclides identified.

The lack of agreement for I-131 could

be attributed to heterogeneous

fractionation of iodine between

the split

fractions.

While the peak stripping routine can

sometimes

cause

anomalous

results to occur, the 364

Kev I-131 peak appears

to be "clean,"

unencumbered

by interfering peaks,

and

a difference of this magnitude

appears

to be too large to attribute to.peak stripping alone.

On the

other hand,

the calibration for this geometry

appears

to be adequate

as

indicated

by the agreement

achieved for the other activities present.

Table

4

Reactor Coolant

Li uid

Nuclide

Na-24

Co-58

I-132

I-133

I-134

I-135

Cs-134

Cs-138

Ba-139

pCi/ml

1.09 E-3

8.24 E-4

~ 3 ~ 05 E-4

, 1.96 E-3

4.17

E-3

4.33

E-3

7. 59 E"3

6. 94 E-3

6.65 E-4

5.33 E-4

2.11 E-2

1.58 E"3

NRC

RCi/ml

1.04 E-3

6.80 E-4

4.62 E-4

2. 02 E-3

4. 56 E-3

4.64 E-3

7.58 E-3

5.73 E-3

5.89 E-4

5.63 E-4

2. 29 E-2

1.86 E-3

Ratio

DCPP/NRC

l. 05

1. 21

0. 66

0. 97

0. 91

0. 93

1. 00

1 ~ 21

1. 13

0. 95

0. 92

0. 85

Agreement

Rancae

0.75 - 1.33

0.60 - 1.66

0.75 - 1.33

0.80 - 1.25

0. 75 " 1. 33

,0

~ 75 - 1.33

0.60 - 1.66

0. 75

1. 33

0.60 - 1.66

The results for a reactor coolant liquid sample

summarized

in Table 4

indicate adequate

agreement for this matrix and this set of nuclides.

Table

5

Sus

ended Solids

Nuclide

Cr-51

Mn-56

Fe-59

Co-58

Ni-65

Zr-95

Zr-97

Nb-95

Nb-97

I-132

I-133

I-135

Cs-134

Cs-138

Sn-117M

Ba-139

p~CiTml

4. 06 E-5

3.20 E-6

1.65 E-5

2. 38 E-6

-6. 72 E-5

9.56

E-6

5. 95 E-6

9. 76 E-6

4. 64 E-6

1.11 E-5

1.16

E-6

2.30 E-6

2.03 E-6

1.59 E-6

6. 52 E-7

1.57 E-5

5. 04 E-7

7. 33 E-6

(April 14,

NRC

pCi7ml

4.51 E-5

3.82 E-6

1.70 E-5

1.80

E-6

8.06

E-5

9. 99 E-6

3.46 E-6

7.00 E-6

1.11 E-5

5.47 E-6

1.22 E-5

1.26

E-6

2.10

E-6

2.52

E-6

2.43

E-6

4.99

E-7

1.58 E-5

4. 10 E-7

8.92 E-7

1987)

Ratio

DCPPGPNRC

0. 90

0. 84

0. 97

1. 32

0. 83

0. 96

0. 85

0. 88

0. 85

0. 91

0. 92

1. 10

0. 81

0. 65

1. 31

0. 99

1. 24

0. 82

Agreement

~Ran

e

0.80 - 1.25

~ 0.75 - 1.33

0.75 - 1.33

0.60 - 1.66

0. 80

1. 25

0.80 - 1.25

0.60 - 1.66

0.80 - 1.25

0.75 - 1.33

0.60 - 1.66

0.75 - 1.33

0.60 - 1.66

0.50 - 2.00

0 ~ 60 - 1.66

0.75 - 1.33

0. 75

1. 33

Tabl e

6

Sus

ended Solids

Nucl i de

Na-24

Cl -51

Mn-56

Fe-59

Co-58

Sn-117M

Zr-95

Zr-97

Nb-95

I-132

I-133"

pCi/ml

3.95

E-7

6. 20 E-5

5.63 E-6

1.96 E-5

2.21 E-6

9.70 E-5

1.35 E-5

8.85 E-7

1.45

E-5

2.33

E-5

1.00

E-5

1.71

E-6

2. 01 E-6

1.39

E-6

(April 16,

NRC

pCi/ml

3.82

E-7

7.42 E-5

6. 27 E-6

2.38 E-5

2.25 E-6

1.12 E-4

1.44 E-5

7.26

E-7

1.73 E-5

2. 63 E-5

1.21 E-5

1.42

E-6

2. 20 E-6

2.48 E-6

1987)

Ratio

DCPP/NRC

1. 03

0. 84

0. 90

0. 82

0. 98

0. 87

0. 94

l. 22

0. 84

0. 89

0. 83

1. 20

0. 91

0. 56

Agreement

~Ran

e

0. 60

1. 66

0.80 - 1.25

0. 80

1. 25

0.75 - 1.33

0. 85 - 1. 18

0.80 - 1.25

0.75 - 1.33

0.80 - 1.25

0.75 - 1.33

I-135

Cs-134

Ba" 139~

Ba-140

W-187

Np"239

3. 12 E-6

8.70 E-7

1.02

E-6

2.02 E-5

3. 03 E-6

1.13

E-6

1.22 E-6

1.39 E-5

2.29 E-6

2.,19 E-6

5 ~ 42 E-7

1. 03

0. 77

0. 84

1. 45

0.75 - 1.33

0 ~ 75-

1 ~ 33

Tables

5 and

6 are the summaries

of results

obtained for suspended

solids

in reactor

coolant.

These

samples

were obtained

by filtering one liter

of reactor coolant through

a 47

mm membrane filter and were obtained to

simulate particulate filter samples.

The particulate filter sample

obtained

from Unit one containment did not provide enough activity to

permit

a meaningful test.

A second

suspended

solids

sample (April 16) was obtained

when

a

measurement

of the first sample with the

new Canberra

gamma spectroscopy

system

(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after sampling) indicated that significant decay

had

taken place

and thus did not contain the spectral

mix desired for this

test.

The Canberra

spectroscopy

system is a recently acquired

system

with new software.

This system

was still in an acceptance

test

mode

and

had not yet been fully calibrated

and thus could not provide quantitative

results.

However,

a peak analysis

report

was obtained for review.

The

peak analysis'appears

to be "standard"

peak analysis

and

as in other

systems,

the

number of peaks identified can vary widely depending

on the

values

chosen for the peak sensitivity parameters.

Licensee

data

shown in Tables

5 and

6 were obtained with the "old" gamma

spectroscopy

system.

Because of operational

needs,

this system

has

been

routinely used

as

a "2 K" system, i.e., spectral

information is collected

in 2048 channels

at 1 Kev per channel

instead of the more conventional

4096 channels

at 0.5

Kev per channel.

While the

2

K mode appears

to

provide adequate

quantitative information in general,

anomalies

can

and

do occur.

For

example,

both I-133 and Ba-139 in Table

6 fail the

agreement test.

Examination of the raw spectral

data

show fully resolved

526

Kev and

529

Kev peaks

in the

NRC measurement.

The 529

Kev line is

the key line for I-133 and the

526

Kev line is a potentially interfering

secondary line from I-135 decay.

The licensee's initial peak analysis

shows

a single

526

Kev line in this region.

In the licensee's

system,

operators

are trained to visually examine

(on the screen)

regions that

appear likely to contain multiplet peaks.

This was

done for this energy

region and

a secondary

peak analysis

was performed using operator

selected

values for beginning

and

end channels for peaks.

A 529

Kev peak

was identified and quantified after the secondary

peak analysis

was

performed.

At 1 Kev per channel,

two peaks

3 Kev apart are separated

by

only two channels.

This situation

does not lend itself to accurate

resolution

and quantification of the peaks,

especially

as the

contribution from the interfering peak

becomes

more significant.

For the

April 14 suspended

solids

samples

(Table 5), better

agreement for I-133

is indicated.

In this case,

however,

the interference

from I-135 was

less

as indicated

by the smaller concentration

of I-135 in this sample.

For Ba-139

(165 Kev) in the April 16 sample

(Table 6), the licensee's

initial peak analysis

showed

a single peak at 159 Kev.

After operator

input, the secondary

peak analysis

indicated

peaks at 158 Kev and

166

Kev.

The 158

Kev line is due to Sn-117M and the 166,Kev line is from

Ba-139.

The

NRC peak analysis

showed three fully resolved

peaks at 158

Kev, 162

Kev (a secondary line from Ba-140)

and 165 Kev.

The problem

here is similar to that for I-133 discussed

above.

It should

be noted that the

NRC measurements

involved longer than normal

counting times to enhance sensitivity and improve counting statistics.

Therefore,

certain ac'tivities not detected

by the licensee

were observed

in the

NRC measurements.

These

have

been included in the tables

only to

show the variety of nuclides present

in these

samples.

Although the overall agreement

is adequate, it could be better,

and the

frequency of anomalies

observed

should

be reduced or eliminated.

It is

expected that all of these

issues will be resolved

when the newly

acquired

spectroscopy

system

becomes fully operational.

This system

can

easily

accommodate

a number of 4

K spectra

or even

8

K spectra

at the

same time.

Specific software modifications are being performed

by the

vendor to conform with the licensee's

specific

needs

and full scale

calibrations

are expected

to commence

soon thereafter.

This system is

expected

to be operational

by early summer.

The

new chemistry laboratory

has

been

completed

and the transfer

and

installation of equipment

and supplies

are in progress.

Space is ample

and the modular structure of the laboratory separates

various laboratory

functions

from each other.

This should

enhance

the laboratory's ability

to perform certain types of trace

measurements.

The equipment is

state-of-the-art,

and laboratory staffing has

been

increased

from a year

ago when the last confirmatory measurements

inspection

was conducted.

This laboratory is expected

to be fully operational within a few months.

The Diablo Canyon chemistry laboratory

does

not participate

in any

external

laboratory cross-check

program directly. It does,

however,

participate in an internal cross-check

program administered

by its

own

Department of Engineering

Research

(DER) in San

Ramon, California.

The

DER in turn does participate in the

EPA cross-check

program.

Exit Interview

Inspection findings were discussed

with licensee

personnel

indicated in

paragraph

1.

It was also indicated that as

a further check

on

measurements

involving beta

and soft x-ray emitters,

a spi ked sample

containing these

and other nuclides would be provided by the

NRC for

analysis

by the licensee

or its vendor laboratory.

(Item No. 87-17-01).

Enclosure

Criteria for Acce tin

the Licensee's

Measurements

Resolution

Ratio

<4

4

-

7

8

-

15

16

-

50

51

- 200

200

0.4

0.5

0.6

0.75

0.80

0.85

2.5

2.0

1.66

1.33

1.25

1.18

~Com arison

Divide each

NRC result by its associated

uncertainty to obtain the

resolution.

(Note:

For purposes

of this procedure,

the uncertainty is

defined

as the relative standard

deviation,

one sigma, of the

NRC result

as calculated

from counting statistics.)

2.

Divide each licensee result by the corresponding

NRC result to obtain

the ratio (licensee

result/NRC).

3

The licensee's

measurement

is in agreement if the value of the ratio

falls within the limits shown in the preceding table for the

corresponding resolu'on.

0

U.

S.

NUCLEAR REGULATORY COMMISSION

REGION V

Report

Nos.

50-275/87-17,

50-323/87-16

Docket Nos.

50-275,

50-323

License

Nos.

DPR-80,

DPR-82

Licensee:

Pacific

Gas

and Electric Company

77 Beale Street

San Francisco,

California

94106

Facility Name:

Diablo Canyon Units

1 and

2

Inspection at:

San Luis Obispo County, California

Inspector:

~

Approved By:

G.

P.

u as,

Chief

Facilities Radiological Protection Section

Inspection

Conducted:

April 13-17,

1987

Cpm

M

H.

Hamada,

Radiation Laboratory Specialist

Date Signed

a

Pg

Date Signed

~Summar

Ins ection of A ril 13-17

1987

Re ort Nos.

50-275/87-17

50-323/87-16

~l:

A

cross-check

measurements.

These

measurements

involved the Region

V Mobile

Laboratory.

The status

of the

new chemistry laboratory

and

new equipment

was

reviewed.

This inspection

covered

Modules

79701

and 84725

'esults:

No items of noncompliance

or deviations

were identified.

DETAILS

1.

Persons

Contacted

'J.

Boots,

Manager,

Chemistry

and Radiation Protection

D.

Chen,

Engineer,

Chemistry

and Radiation Protection

"J.

E. Gardner,

Sr.

Engineer,

Chemistry

and Radiation Protection

"F.

A. Guerra,

Foremen,

Chemistry

"M. Hug, Engineer,

Regulatory

Compliance

"R.

L. Johnson,

General

Foreman,

Chemistry

"D. Unger,

Radiochemical

Engineer

"Indicates personnel

present at exit interview.

2.

Discussion

The

NRC mobile laboratory

was brought onsite to perform cross-check

measurements

on selected

sample categories

for which radioactivity

measurements

are required.

The results

are

summarized

below:

Table

1

Waste

Gas

in Glass

Bulb

Nuclide

Xe-133

Xe-131M

OCi/cc

1.15 E-2

4.58 E-4

NRC

PCi/CC

1.55 E-2

5.64

E"4

Ratio

DCPP/NRC

0. 74

0. 81

"Agreement

Rancae

0.75 - 1.33

0. 60 - 1. 66

"See enclosure for explanation.

The results in Table

1 indicate marginal

agreement for the waste

gas

category.

The

NRC calibration for the glass

bulb geometry,

however,

was

performed with a glass

bulb of slightly different capacity

and wall

thickness

than the bulb used to obtain this sample.

Given the

uncertainties

associated

with this measurement,

the agreement

is

adequate.

Table

2

Iodine Cartrid e

Nuclide

I-132

I-133

I-135

BR-82

OCiciml

6.14 E-10

5.10 E"11

2.61 E-10

9.97 E-11

1.89 E"10

NRC

RMCi ml

5.04 E-10

2.44 E-ll

2.00 E-10

1.07 E-10

1.13 E-10

Ratio

OCPPTNRC

1. 22

2. 09

l. 31

0. 93

l. 67

Agreement

~Ran

e

0.75 - 1.33

0.40 - 2.50

0.60 - 1.66

0.50 - 2.00

0.60 - 1.66

Table

2 lists the results

obtained for the iodine cartridge

geometry.

Because

Diablo Canyon routinely uses silver zeolite for iodine

collection,,a silver zeolite cartridge rather than

a charcoal

cartridge

was

used for this test.

The .low activities observed

in this sample

are

reflected

by the relatively wide agreement

range indicated in the table.

In general,

the agreement

is adequate.

Table

3

Li uid Waste

Nuclide

NCl/ml

NRC

Ratio

Agreement

NCi7ml

DCPP/NRC

,

.

~Ran

e

Co-57

Co-58

I"131

Cs"134

8.54 E-7

2.89 E-7

1.07 E-4

8.54 E-6

7.52 E-6

1.50 E-6

1.81 E-6

1.16 E-6

1.65 E-7

1.20 E-4

9.43 E-6

1.30 E-5

1.83 E-6

2.33 E-6

0 ~ 74

1. 75

0. 89

0. 91

0. 58

0. 82

0. 78

0.60 - 1.66

0.40 " 2.50

0.80 - 1.25

0.75 - 1.33

0. 75 - l. 33

0.60 - 1.66

0. 60 - 1. 66

The results for split samples

of chemical drain tank liquid waste

are

summarized in Table 3.

Except for I-131, adequate

agreement

is indicated

for all other nuclides identified.

The lack of agreement for I-131 could

be attributed to heterogeneous

fractionation of iodine between

the split

fractions.

While the peak stripping routine can sometimes

cause

anomalous

results to occur,

the

364

'".',ev I-131 peak appears

to be "clean,"

unencumbered

by interfering peaks,

and

a difference of this magnitude

appears

to be too large to attribute to'eak stripping alone.

On the

other hand,

the calibration for this geometry appears

to be adequate

as

indicated

by the agreement

achieved for,the other activities present.

Table

4

Reactor Coolant

Li uid

Nuclide

Na-24

Co-58

I"131

I-132

I"133

I"134

I"135

Cs-134

Cs-138

Ba"139

NCl/ml

1.09 E-3

8.24 E"4

3.05 E-4

1.96 E-3

4.17 E-3

4.33 E-3

7.59 E-3

6.94 E-3

6.65 E-4

5.33 E-4

2.11 E-2

1.58

E-.3

NRC

NCi/ml

1.04 E"3

6.80 E-4,

4.62 E"4

2.02 E-3

4.56 E-3

4.64 E-3

7.58 E-3

5.73

E"3

5.89 E"4

5.63 E-4

2.29 E-2

1.86 E-3

Ratio

DCPP/NRC

1. 05

l. 21

0. 66

0. 97

0. 91

0. 93

1. 00

1. 21

l. 13

0. 95

0 ~ 92

0. 85

Agreement

~Ran

e

0.75 - 1.33

0. 75 - 1. 33

0.60 " 1.66

0.75 - 1.33

0.80 - 1.25

0.80 " 1.25

0.75 " 1.33

0.60 - 1.66

0.75 - 1.33

0.60 " 1.66

t

The results for a reactor coolant liquid sample

summarized

in Table

4

indicate adequate

agreement for this matrix and this set of nuclides.

Table

5

Nuclide

~~Ci

ml

Sus

ended

April 14,

NRC

RCi7ml

Solids

1987

Ratio

D~CPP

NRC

Agreement

~Ran

e

Cr-51

Mn-56

Fe-59

Co-58

Ni-65

Zr"95

Zr-97

Nb-95

Nb-97

I-132

I-133

I"135

Cs-134

Cs-138

Sn-117M

Ba-139

4.06 E-5

3. 20 E-6

1.65 E-5

2. 38 E-6

6. 72 E-5

9. 56 E-6

5.95 E-6

9.76 E-6

4.64 E-6

1.11 E-5

1.16 E-6

2. 30 E"6

2. 03 E-6

1.59 E-6

6.52

E-7

1.57 E-5

5.04 E-7

7.33 E-6

4.51 E-5

3.82 E-6

1.70 E-5

1.80 E"6

8.06

E"5

9.99 E-6

3.46 E-6

7. 00 E-6

1.11 E-5

5.47 E-6

1.22 E-5

1.26 E-6

2 ~ 10 E-6

2. 52 E-6

2.43

E"6

4.99

E"7

1.58 E-5

4.10 E-7

8.92 E"7

Table

0. 90

0. 84

0. 97

1. 32

0. 83

0. 96

0. 85

0. 88

0. 85

0. 91

0. 92

1. 10

0. 81

0. 65

1. 31

0. 99

l. 24

0. 82

0.80 - 1.25

0.75 - 1.33

0. 60

1. 66

0. 80 " 1. 25

0,80 - 1.25

0.60 - 1.66

0.80 - 1.25

0.75 - 1.33

0.60 - 1.66

0.75 " 1.33

0.60 - 1.66

0.50 - 2.00

0.60 - 1 ~ 66

0.75 -

1.33'.75

- 1.33

Nuc-l ide

Na" 24

Cr-51

Mn-56

Fe-59

Co"58

Co-60-

Sn-117M

Zr-95

Zr-97

Nb"95

I"131

I"132

I-133"

~Ci /ml

3.95 E-7

6.20 E-5

5.63 E-6

1.96 E-5

2.21 E-6

9. 70 E"5

1.35 E-5

8.85 E-7

1.45 E-5

2.33 E-5

1.00 E"5

1.71 E"6

2.01 E-6

1.39 E-6

Sus

ended

(April 16,

NRC

~Ci7ml

3.82 E-7

7.42 E-5

6.27 E-6

2.38 E-5

2.25 E-6

1.12 E-4

1.44 E"5

7.26 E-7

1.73 E"5

2.63

E"5

1.21 E-5

1.42 E-6

2.20 E"6

2.48 E-6

Solids

1987)

Ratio

DCPP/NRC

1. 03

0. 84

0. 90

0. 82

0. 98

0. 87

0. 94

1. 22

0. 84

0. 89

0. 83

1. 20

0. 91

0. 56

Agreement

~Ran

e

0.60 - 1.66

0.80 - 1.25

0.80 " 1.25

0. 75 - 1. 33

0.85 - 1.18

0.80 - 1.25

0.75 - 1.33

0.80 - 1.25

0. 80 " 1. 25

0.80 - 1.25

0.75 - 1.33

I-135

Cs-134