ML16341E853

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Insp Repts 50-275/88-27 & 50-323/88-25 on 881003-07. Strengths & Weaknesses Noted.Major Areas Inspected:Qa for Chemistry Activities,Water Chemistry Control,Chemical & Radiochemical Analyses & Onsite Followup of Inspector Items
ML16341E853
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 10/31/1988
From: North H, Tenbrook W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML16341E854 List:
References
50-275-88-27, 50-323-88-25, IEIN-83-33, NUDOCS 8811160184
Download: ML16341E853 (12)


See also: IR 05000275/1988027

Text

U.

S.

NUCLEAR REGULATORY COMMISSION

REGION V

Report Nos.

50-275/88-27

and 50-323/88-25

License

Nos.

DPR-80 and

DPR-82

Licensee:

Pacific Gas

and Electric Company

77 Beale Street

Suite 1451

San Francisco,

California 94106

Facility Name:

Diablo Canyon

Power Plant - Units 1 and

2

Inspection at:

Diablo Canyon Site - Seven Miles North of Avila Beach,

California

Inspection

Conducted:

October 3-7,

1988

Inspected

by:

W.

K. TenBrook, Radiation Specialist

/o/M/$$

'ate

Signed

Approved by:

H.

S. North, Acting Chief

Faci 1 ities

Radi ol ogi cal Protecti on Section

Date

igned

~Summa m

chemistry activities, water

chemistry control, chemical

and radiochemical

analyses,

and onsite follow-up of inspector-identified

items.

Inspection

procedures

30703,

84750

and 92701 were addressed.

Results:

Strengths

were observed in the following areas:

Control of ionic

impurities in the secondary

system,

improvement of water chemistry regimes for

primary and secondary

systems.

Weaknesses

were observed in condensate

dissolved

oxygen control

and timeliness of actions

by gA and chemistry

departments

pursuant to audit findings.

Overall, the licensee's

chemistry

program performance

was satisfactory in accomplishing

tasks

important to

safety.

8811160184

881031

PDR

ADOCK 05OOOP75

G

PNU

0

DETAILS

Persons

Contacted

Licensee

P. Baxter, Instructor, Technical

8 Maintenance Training

  • J. Boots,

Manager,

Chemistry

K. Cortese,

Chemistry

Foreman

"K. Doss,

Senior Engineer; Onsite Safety Review Group

  • C. Eldridge,

Manager, quality Control

"J. Gardner,

Senior Engineer,

Chemistry

  • J. Gisclon, Assistant Plant Manager,

Support Services

L. Goyett,

Engineer,

Onsite Engineering

F. Guerra,

Radiochemistry

Foreman

"R. Harris, Supervisor, guality Assurance

Audits

R. Johnson,

General

Chemistry

Foreman

"W. Kelly, Engineer,

Regulatory Compliance

M. Leppke, Onsite Project Engineer

"J. Shoulders,

Assistant Onsite Project Engineer

'"D. Taggart, Director, guality Support

H. Thailer,

Lead Engineer,

Corporate

Engineering

E. Wessel,

Chemical

Engineer

  • L. Womack, Assistant Plant Manager,

Operations

Contractor

J. Bellows, guality Assurance

Consultant,

Cygna

USNRC

P. Narbut, Senior Resident Inspector,

Diablo Canyon

Fol 1 ow-u

(92701

0 en Item 50-275/87-24"Ol

OPEN

This item concerned

the clarification

of criteria for decisions

to repair secondary piping thinned by

erosion/corrosion.

The licensee

had not addressed

this issue, citing a

lack of reliable pipe wall thinning data

and the absence

of

widely-accepted criteria for repair and replacement

decisions.

During

the interim, the licensee relied upon case-by-case

evaluations

to make

pipe repair and replacement

decisions.

The licensee

stated that an

Engineering Instruction addressing

pipe repair and replacement

decisions

would be issued following Unit 2 piping inspections

and the March 1989

meeting of the Erosion/Corrosion

Task Force.

The licensee

agreed to

supply

a written commitment describing the timetable for issuance

of the

Engineering Instruction.

This item will remain

open pending

NRC review

of the Engineering Instruction regarding pipe repair, and replacement

decisions.

0

A.

Water Chemistr

and Radiochemical

Anal sis

84750

The inspector

reviewed the involvement of the licensee's

guality

Assurance

and guality Control organizations

in the chemistry

and

radiochemistry

areas

pursuant to 10 CFR 50, Appendix

B and ANSI-N18. 7.

The last programmatic audit covering these

areas

was documented

in audit

report 87093T,

dated July 30, 1987, which fell within the designated

two

year audit cycle.

One Audit Finding Report,

AFR 87-126,

stated that

quality-related

and safety-related

chemistry activities

had not been

defined pursuant to administrative procedures.

The licensee

had deliberated

over this audit finding for fifteen months

without resolution.

The Chemistry Department

had been reluctant to

classify procedures

as safety-related

or quality-related

and hence

be

required to revise the designated

procedures

to comply with the

gA

Manual, insisting that certain

gA Manual requirements

were inappropriate

for nuclear chemistry activities.

As an alternative,

the Chemistry

Department

had drafted

a gA Manual procedure

intended to guide auditing

personnel

in evaluating chemistry activities.

During the inspection,

negotiations

were proceeding

between guality Assurance

and Chemistry

on

defining safety-related

chemistry procedures

versus

the acceptability of

the draft gA manual

procedure

on chemistry.

The inspector also reviewed

a sample of guality Assurance

technical

specification surveillance

reports

and guality Control surveillance

reports for the period January

1988 to the date of the inspection.

No

technical specification

(TS) noncompliance

was identified within the

sample.

guality Control surveillance

88-39 identified problems involving

attention to detail during Reactor Coolant System

(RCS) hydrogen

analyses.

These

problems

appeared

unrelated to other difficulties in

RCS

hydrogen control described

in Section 2.B., below.

The licensee

also

addressed

INPO findings in the

gC surveillance

program.

The involvement of guality Assurance

and guality Control in the chemistry

area

has

been satisfactory.

However,

some outstanding

gA findings had

not been expeditiously resolved.

The Chemistry and

gA

Departments'nability

to reach

a satisfactory

compromise with regard to gA

requirements

in the chemistry area

suggests

a weakness

in the licensee's

ability to promptly integrate specialized plant activities into their

overall

gA oversight program.

B.

Water Chemistr

Control

and Anal sis

The inspector

reviewed monthly reports of chemistry data,

laboratory

logs,

and observed

instrument indications during tours to assess

overall

chemistry performance with respect to the technical specifications,

EPRI

and vendor guidelines,

and licensee

procedures.

RCS ionic impurities were held well below action levels,

and chloride

levels were particularly low.

RCS

TS fluoride levels were not

approached,

but occasionally

appeared

in chemistry data at levels below

0

the 50 ppb detection limit f'r the specific ion electrode

method

employed.

The licensee

had identified continuing problems involving RCS hydrogen

control.

The inspector

noted that the licensee's

target control

band of

30-40 cc/kg

RCS dissolved

hydrogen is relatively restrictive,

and

approximated

the

EPRI

recommended

25-35 cc/kg for alloy 600 steam

generator

tubes.

Over the past year, operating unit RCS hydrogen levels

were out of the procedural

control

band from 10K to 30K of the time.

To

improve hydrogen control, the licensee

had decreased

the high pressure

alarm setpoint

on the volume control tank (VCT) and incr eased

hydrogen

addition regulator settings,

as well as improving communications

between

operations

and chemistry.

The inspector

observed that Unit 1 operating

'hydrogen levels were generally within the control

band the month prior to

the inspection, exhibiting improved performance.

Corrective actions for

Unit 2 were to be completed prior to startup.

Licensee

procedure

OP F-5: I, "..

~ Control Limits and Action Guidelines for

Primary Systems...,"

contained

a new lithium/boron coordinated

chemistry,

which provided

an

RCS

pH increase

from 6.9 to 7.5 during the middle and

later portions of the operating cycle.

This

pH regime would decrease

deposition rates of corrosion products

on

RCS surfaces,

hence decreasing

radiation

dose rates in and around

RCS components.

The inspector

noted that the licensee's

coordinated

RCS lithium

concentration

band at the beginning of the. cycle did not provide for a

RCS

pH of 6.9 or above,

as

recommended

in the

EPRI Primary Water

Chemistry Guidelines.

The inspector

reviewed

a letter

from the

licensee's

reactor/fuel

vendor,

dated August 2, 1988, which contained the

approved lithium control program.

The program specified

a pH lower than

6.9 prior to constant lithium operation in order to conservatively

decrease

the risk of primary water stress

corrosion cracking

(PWSCC)

due

to sustained

high

RCS lithium concentration.

Ionic impurities in secondary

water systems

had generally decreased,

in

terms of ppb-days'eriodic

excursions of sulphate

and sodium were

observed

in condensate

polisher discharge

and steam generator

blowdown,

associated

with operating transients.

The excursions

were generally

attributed to polisher operation

and reappearance

of hide-out from

previous polisher impurity ingress.

Concentrations

greater

than action

level

one were corrected within one week of diagnosis,

per procedure

OP

F-5: II, "Chemistry...Action Guidelines for Secondary

Systems".

Condensate

dissolved

oxygen frequently exceeded

action levels.

This

condition had been attributed to condensate

system inleakage,

and the

licensee

had taken appropriate

steps

to identify such leakage.

However,

recent contractor studies

suggested

that the condenser air removal

system

was inefficient, allowing significant dissolved

oxygen concentrations

to

remain in the condensate.

Preliminary results

indicated that the

inefficiency was caused

by fouling of the condenser

near the air

ejectors,

causing air binding, high and uneven hotwell water level,

inappropriate location of condensate

polisher recycle line discharge,

and

low-biased instrument indications of offgas flow rate.

The inspector

will examine the licensee's

actions to improve condensate

dissolved

oxygen performance

during a future inspection

(50-275/88-27-01).

The licensee

had initiated a boric aci'd addition program for secondary

water at the request of their,steam generator

vendor.

The boric acid

addition is intended to prevent tube denting by borate intrusion into

crevices

and pores,

passivating

the surface,

and thereby preventing

attack by other chemical

species.

Secondary water chemistry effects were

generally subtle,

except for a changed relationship

between specific

conductivity and

ammonia concentration.

The inspector calculated

the

peak boron injection rate

as approximately equivalent to the boron

ingress to the steam generators

resulting from the

TS identified leakage

limit, 10 gpm, at 1000

ppm boron operation.

Given the low boron

concentrations

involved, the process

did not appear to impair any'afety

systems

or place

systems

in an unanalyzed

condition.,

The inspector frequently toured the primary and secondary

system

laboratories

and the condensate

polisher

rooms during the inspection.

The secondary

water chemistry laboratory

was

a significant addition to

chemistry facilities.

The inspector

observed that housekeeping

in the

primary water laboratory

had improved since previous inspections,

as the

new laboratory performed

much of the secondary

system analytical

workload.

Fume

hood flow and

maximum sash

openings

were uniformly

established,

but some secondary

lab hood sashes

were left wider than

maximum.

No wet chemistry activities were observed

in hoods

opened

beyond

maximum.

Coats

and safety glasses

were worn within all

laboratories.

A precautionary frisk was required to exit the secondary

lab, located outside the controlled area

boundary.

The inspector

examined the instrumental

control program for water

chemistry analyses.

RCS fluoride, by the specific ion electrode

method,

had exhibited

some off-normal behavior with independent

control standards

at 20 ppb, which was at or beyond the sensitivity of the technique.

Control standard

concentration

was changed to 100 ppb, which was within

the capabilities

of the method,

and response

was

improved.

Also, the

licensee

now considers

instrumental

systematic

bias in control chart

evaluation

by identifying seven consecutive

control points

above or below

the

mean

as

a bias trend.

The inspector

reviewed the results of chemical analysis

intercomparisons

conducted

using spiked samples

from a vendor laboratory.

Poor results

were obtained for the intercomparison of a secondary

water matrix sample

containing

20 ppb fluoride.

The licensee

did not routinely perform

fluoride analysis for secondary water,

and the specific ion electrode

(SIE) method

was routinely used for RCS fluoride.

The poor

intercomparison

results reflected the 50 ppb fluoride detection limit by

SIE.

Although it was agreed that SIE was acceptable

for routine

RCS

fluoride, the licensee

stated it was their intention to use ion

chromatography to improve the accuracy

and sensitivity of routine

fluoride analyses.

The licensee

had implemented

a superior program for control of primary

and secondary

water chemistry, chiefly by the prompt implementation of

improved

RCS coordinated

chemistry,

boron passivation

for steam

0

generators,

and incremental

reduction of secondary

water impurities.

Weak areas

remained in condensate

oxygen control,

and the improving

effectiveness

of VCT hydrogen control.

Radiochemical

Anal sis

The inspector

reviewed the licensees

procedures

and practices for

sampling

and analysis of waste oil and other mixtures.

Procedure

RCP

D-611, "...Release

of...Sludges,

Slurries

and Oils from the

RCA,"

instructed radiation protection personnel

to mix these

wastes

thoroughly,

but also cautioned

the reader to take samples of each

phase

when mixing

was not achievable.

Criteria for unconditional

release

were less

than

0.1 pCi/ml

gamma activity, less

than

1000 pCi/ml tritium, and

administrative

approvals.

The procedure

addressed

NRC Information Notice

IN-83-33, "Nonrepresentative

Sampling of Contaminated Oils."

The inspector verified that adequate

measurement

control checks

were

performed for radioanalytical

instruments

per procedures

and industry

standard practices.

Areas for improvement regarding width of control

limits were being addressed

in response

to recent

independent

audit

findings.

The inspector

conducted tours of the 85'levation of the Auxiliary

Building, principally to observe

operation of the Unit One Post Accident

Sampling System

(PASS).

Area radiation monitors

and air monitors were

observed to be within their calibration dates,

and postings

were properly

maintained.

The inspector

observed

reactor coolant

and containment

atmosphere

sampling using the

PASS during a training exercise.

Boron

concentrations

obtained

by the carminic acid method in the

PASS

laboratory were in excellent

agreement

with routine measurements.

The

Inspector also reviewed attachments

to Surveillance Test Procedure

STP

G-14 which contained

intercomparisons

for all measurements

required

by

NUREG-0737, II.B.3. for the period January to June

1988.

Intercomparison

with routine measurements

indicated that representative

samples

and

accurate

measurements

were obtained using

PASS equipment for those

concentrations

observable with PASS lab techniques.

The licensee's

program for radiochemical

measurements

was satisfactory.

Procedures

for sampling two-phase mixtures were considered

superior,

given that personnel

properly follow instructions for sampling each

phase

as necessary.

Exit Meetin

30703

The Inspector

met with licensee

management

on October 7, 1988, to discuss

the scope

and findings of the inspection.

The inspector

recognized that-

the resolution of AFR 87-126 remained subject to continued internal

negotiation.

However, the inspector also stated that programmatic audits

of the chemistry program were expected to be performed

as required,

and

should not to be delayed contingent

on the resolution of past audit

findings, including AFR 87-126.

The inspector

also confirmed that the

licensee

would prepare

and submit

a written commitment containing

a

schedule

for issuance

of a pipe repair/replacement

decision instruction.