ML14176A745

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Insp Rept 50-261/89-10 on 890511-0613.Violation Noted. Major Areas Inspected:Maint Observation,Esf Sys,Walkdown & Emergency Diesel Generator Fuel Oil Quality
ML14176A745
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 07/07/1989
From: Dance H, Garner L, Jury K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML14176A744 List:
References
50-261-89-10, NUDOCS 8907180383
Download: ML14176A745 (8)


See also: IR 05000261/1989010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION il

101 MARIETTA ST., N.W.

ATLANTA, GEORGIA 30323

Report No.:

50-261/89-10

Licensee:

Carolina Power and Light Company

P. 0. Box 1551

Raleigh, NC 27602

Docket No.:

50-261

License No.: DPR-23

Facility Name: H. B. Robinson

Inspection Conducted: May 11- June 13, 1989

Inspectors:71

/9

L. W. Garner, Senior R

enX4 nspector

Oatd Signed

K- R Jury

Resident I f0ectof

Da e Signed

Approved by:

__

4_____

7/I

H. C. Dance, Section Chief

te Signed

Division of Reactor Projects

SUMMARY

Scope:

This routine, announced inspection was conducted in the areas of operational

safety verification, surveillance observation, maintenance observation,

engineered safety feature system walkdown,

and emergency diesel generator fuel

oil quality.

Results:

Breakdowns in the licensee's corrective action program were identified.

A

violation was issued for failure to promptly identify and correct three

conditions adverse to quality, paragraph 2.a and b.

Repair activities of the B component cooling system heat exchanger were well

planned and coordinated, paragraph 2.a.

9O718038 890707

GDR ADOCK 05000261

PNU

REPORT DETAILS

1. Persons Contacted

  • D. Crook, Senior Specialist, Regulatory Compliance
  • J. Curley, Director, Regulatory Compliance

C. Dietz, Manager, Robinson Nuclear Project

J. Eaddy, Supervisor, Environmental and Chemistry

R. Femal , Shift Foreman, Operations

W. Flanagan, Manager, Design Engineering

W. Gainey, Supervisor, Operdtions Support

  • E. Harris, Director, Onsite Nuclear Safety

D. Knight, Shift Foreman, Operations

D. McCaskill, Shift Foreman, Operations

R. Moore, Shift Foreman, Operations

R. Morgan, Plant General Manager

  • C. Mosely, Corporate Manager, Operations Quality Assurance

D. Myers, Shift Foreman, Operations

D. Nelson, Maintenance Supervisor, Mechanical

R. Powell, Engineering Supervisor, Technical Support

  • D. Quick, Manager, Maintenance

D. Seagle, Shift Foreman, Operations

  • J. Sheppard, Manager, Operations

R. Steele, Operations Coordinator

D. Winters, Shift Foreman, Operations

  • H. Young, Director, Quality Assurance/Quality Control

Other licensee employees contacted included technicians, operators,

mechanics, security force members, and office personnel.

  • Attended exit interview on June 21, 1989.

Acronyms and initialisms used throughout this report are listed in the

last paragraph.

2. Operational Safety Verification (71707)

The inspectors evaluated licensee activities to confirm that the facility

was being operated safely and in conformance with regulatory requirements.

These activities were confirmed by direct observation, facility tours,

interviews and discussions with licensee personnel

and management,

verification of safety system status, and review of facility records.

To verify equipment operability and compliance with TS,

the inspectors

reviewed shift logs, operation records, data sheets, instrument traces,

and records of equipment malfunctions.

Through observations of work and

discussions with operations staff members,

the inspectors verified the

staff was knowledgeable of plant conditions, responded properly to alarms,

2

adhered to procedures and applicable administrative controls, cognizant of

in-process surveillance and maintenance activities, and aware of inoperable

equipment status.

The inspectors performed channel verifications and

reviewed component status and safety-related parameters

to verify

conformance with TS.

Shift changes were routinely observed.

Access to

the control room was controlled and operations personnel carried out

their assigned duties effectively.

Plant tours and perimeter walkdowns were conducted to verify equipment

operability, assess the general condition of plant equipment,

and to

verify that radiological controls, fire protection controls, physical

protection controls,

and equipment tagging procedures were properly

implemented.

a. CCS Leakage Into The SW System

On June 2, 1989, while conducting a survey on closed cooling systems,

the inspectors identified that the CCS surge tank was being made-up

on an abnormally frequent basis.

Water is normally only added to

the CCS after maintenance which requires partial system draining.

Operations personnel informed the inspectors that the surge tank was

being made-up (i.e., reaching 45% low level alarm set-point and being

filled to approximately 50% level) every two weeks. Upon questioning

the effect these additions had on CCS chemistry, the inspector

contacted the Chemistry Department; the Chemistry Department was

unaware of these additions.

The CCS chemistry was then analyzed and

found to be out of specification for both chromates (corrosion

inhibition) and ph.

These two parameters are monitored to prevent

corrosion and fouling of the CCS piping and components, which could

result in decreased CCS heat removal capability. Upon investigation,

it was determined that approximately 100 gallons were being added to

the CCS approximately every 2 1/2 days since April 30,

1989.

The

unusual number of additions indicated that there was leakage from the

CCS. The inspectors questioned Operations about possible CCS leakage

pathways. The inspector and an SRO walked down portions of the CCS

piping outside of Cv; however, the leakage source was not located.

Chromates were not identified in the waste hold-up tank, which would

have indicated a leak inside of Cv.

After returning chromate concentrations and ph to within specifica

tions, Chemistry monitored chromate concentrations in the CCS on a

daily basis for the next five days.

It was determined that the

chromate concentration was continually decreasing, verifying the

presence of a leak.

On June 6, Operations isolated the A and B CCS

heat exchangers and discovered that B heat exchanger was, in fact,

leaking into the SW system. On June 13, during repairs to the B CCS

heat exchanger, six tubes were found to be leaking and were

subsequently plugged.

This repair effort was well planned and

coordinated effectively between Operations, Maintenance and Chemistry.

3

The Chemistry Department was prompt in responding to the inspectors'

concerns and communicated effectively with Operations concerning this

matter.

Since the repair, there has been no further indications of

CCS leaks.

This situation resulted in several problems being identified.

The

first has to deal with operator recognition that there was a leak

from the CCS. The licensee's operation shift schedule is not conducive

to one particular shift recognizing the unusual number of times

additions were made to the CCS; all but two of the required log

entries were recorded into the CO's log book.

At the end of each

shift the shift foreman initials the log entries for that respective

shift, acknowledging cognizance of the evolutions performed.

Additionally, as part of shift turnover, the oncoming CO documents

that he/she has "reviewed previous shifts logs".

As a result, each

time a CCS addition was logged, at least three individuals were

acknowledging each respective make-up that was logged.

Between

April 30 - June 2, 1989, there were at least thirteen make-ups to the

CCW system; thus, there were thirty-nine instances (sometimes the same

operators) of implicit acknowledgement of CCS make-ups occurring.

Additionally, there is not evidence that these additions were verbally

communicated between shifts. There was not an investigation/corrective

action initiated until June 2, 1989, when the possibility of a CCS

leak was raised by the inspectors. The failure to promptly identify

and correct the CCS leak is a violation:

Failure to Promptly Identify

and Correct Conditions Adverse to Quality, 89-10-01.

The

fact

that

there

was

not a control

mechanism

triggering Operations to notify the Chemistry department when a CCS

addition was performed, resulted in CCS chemistry being driven out of

specification and delaying prompt leakage identification. Chemistry

samples the CCS on a monthly basis, and if not notified when the

system chemistry is diluted, has no control over maintaining chemistry

specifications.

Corrective action for this violation should address

this problem.

b. Inadequate and Untimely Corrective Action on Valves TCV-144 and

CC-832

As part of the CCS walkdown,

the non-regenerative heat exchanger

piping and valves were inspected to verify the absence of potential

leakage sources.

The inspector noted a deficiency tag written on

TCV-144, the non-regenerative heat exchanger outlet TCV, indicating

that the valve had a packing leak. Upon inspection (by the inspector,

4

an SRO,

and regulatory compliance) it was determined that the valve

was not leaking.

Review of the past year's WRs on this valve

revealed the following sequence of events:

WR/JO#

Date

Problem Identified

Corrective Action

Implemented (Date)

88-AJHC1

09/07/88 Valve failed stroke

New packin

test

installed (9/12/88)

88-AKHJ1

10/02/88 Valve has a packing

Adjusted packing to

leak

stop leak (10/17/88)

89-AEGC1

04/07/89 Valve failed stroke

Shaft lubricated and

test

packing glands

loosened (04/08/89)

89-AFCM1

05/13/89 Valve has a packing

Adjusted packing to

leak

stop leak (05/31/89)

89-AFMJ1

05/31/89 Valve failed stroke

Lubricated stem and

test

loosened packing

glands (06/13/89)

Based on the above sequence of events, it appears that the corrective

action implemented for each respective WR had an adverse effect on

the valve, resulting in the subsequent WR being initiated.

In

addition, after the packing was adjusted to stop the leak on

October 17, 1988, there was not a post-maintenance test performed to

verify the valve would stroke in the required time.

The failure to

take adequate corrective action to preclude this situation from

recurring (i.e., failing to stroke, packing leak, failing to stroke,

etc....) is considered an example of Violation 89-10-01, Failure to

Promptly Identify and Correct Conditions Adverse to Quality.

While reviewing the

CCS leak discussed in paragraph 2.a,

the

inspectors noted that Valve CC-832, the CCS surge tank make-up valve,

did not always fully close (with the PW pump running) after the CCS

was made-up; thus, allowing an excessive amount of PW to enter the

surge tank.

This condition could mask a leak out of the system,

exacerbated chromate concentration dilution of the system,

and

prevented an accurate leakage rate from being determined.

The

failure of this valve to fully close was first identified in February

1988. Subsequent to this identification, WR 88-AEKC1 was written on

April 9, 1988. On April 13, 1988, EWR 324 was written by maintenance

addressing the fact that no torque switch setting was provided in the

WR nor in procedure CM-111 Rev. 5, Limitorque Limit Switch and Torque

Switch Maintenance.

Maintenance. requested Engineering action by

eI

5

May 1, 1988, as the "leaking valve could possibly cause the CCS surge

tank to overfill."

As of June 8, 1989,

the Technical Support

Department had not dispositioned this EWR for resolution, as it was

not considered a priority work item. However, after discussions with

several operators, it became apparent that this valve had not fully

closed on several occasions, resulting in the CCS surge tank reaching

its high level alarm setpoint. The operators have had to perform the

abnormal evolution of closing this valve after stopping the PW pump

(versus closing the valve then stopping the pump) for the past

sixteen months. According to the operators, this evolution was not

always performed correctly or the valve would not fully close,

resulting in the overfills described above. The fact that Engineering

did not perform an evaluation of this valve's inability to close for

over sixteen months is considered another example of Violation

89-10-01, Failure to Promptly Identify and Correct Conditions Adverse

to Quality.

One violation, with three examples, was identified.

3. Monthly Surveillance Observation (61726)

The inspectors observed certain safety-related surveillance activities on

systems and components to ascertain that these activities were conducted

in accordance with license requirements.

For the surveillance test

procedures listed below, the inspectors determined that precautions and

LCOs were adhered to; the required administrative approvals and tagouts

were obtained prior to test initiation; testing was accomplished by

qualified personnel in accordance with an approved test procedure; test

instrumentation was properly calibrated; the tests were completed at the

required frequency; and that the tests conformed to TS requirements. Upon

test completion,

the inspectors verified the recorded test data was

complete, accurate, and met TS requirements; test discrepancies were

properly documented and rectified; and that the systems were properly

returned to service.

Specifically, the inspectors witnessed/reviewed

portions of the following test activities:

o

OST-10 (revision 9)

Power Ranger Calorimetric During Power

Operation

o

OST-051 (revision 10)

Reactor Coolant System Leakage Evaluation

o

OST-905 (revision 4)

Reactor Coolant Flow Protection Channel

Testing

No violations or deviations were identified.

6

4. Monthly Maintenance Observation (62703)

The inspectors observed safety-related maintenance activities on systems

and components to ascertain that these activities were conducted in

accordance with TS,

approved procedures,

and appropriate industry codes

and standards.

The inspectors determined that these activities did not

violate LCOs and that required redundant components were operable.

The

inspectors verified that required administrative, material,

testing,

radiological, and fire prevention controls were adhered to.

In addition

to those WRs discussed in paragraph 2, the inspectors also observed/reviewed

the following maintenance activities:

o

MST-006 (revision 4)

Reactor Coolant Flow Protection Channel

Testing

0

WR/JO 89-AETP1

Repair FT-436C Instrument Loop

No violations or deviations were identified, except as noted in

paragraph 2.

5. ESF System Walkdown (71710)

The inspectors performed a field walkdown of selected portions of the SW

system

shown

on drawings

G-190199

sheets 3,5,6,7,9,10, and

11.

Specifically, the inspectors examined selected components in the SI pump

room, CCS room, auxiliary building, and turbine building.

Items examined

included pumps,

valves, piping, pipe supports,

instrument tubing, and

component tagging.

The inspectors verified that major valves were in their

correct position, manual valves were locked as required, and instrumenta

tion was valved into service.

No-violations or deviations were identified.

6. Proper Receipt, Storage, and Handling of EDG Fuel Oil (255100)

In reviewing the EDG fuel oil controls, the inspectors reviewed the

licensee's Operations QA/QC Surveillance Report 89-019, Proper Receipt,

Storage,

and Handling of Emergency Diesel Generator Fuel Oil.

This

surveillance verified compliance to FSAR and TS requirements and commit

ments concerning EDG fuel oil.

The inspectors also reviewed the ONS OEF

Evaluation of IEN 87-04, Diesel Generator Fails Test Because of Degraded

Fuel.

The surveillance report adequately detailed how -the licensee

addressed the questions contained in TI 2515/100 Appendix A.

The QA/QC

surveillance appeared to be very thorough and all discrepancies identified

were documented and tracked within the licensee's corrective action

program.

No violations or deviations were identified.

________________________________I

7

7. Exit Interview (30703)

The inspection scope and findings were summarized on June 21, 1989, with

those persons indicated in paragraph 1.

The inspectors described the

areas inspected and discussed in detail the inspection findings listed

below and in the summary. Dissenting comments were not received from the

licensee. Proprietary information is not contained in this report.

Item Number

Description/Reference Paragraph

89-10-01

VIO - Failure to Promptly Identify and Correct

Conditions Adverse to Quality (paragraph 2.a

and b)

8. List of Acronyms and Initialisms

CCS

Component Cooling System

CFR

Code of Federal Regulations

CM

Corrective Mainteance

CO

Control Operator

Cv

Containment

EDG

Emergency Diesel Generator

ESF

Engineered Safety Feature

EWR

Engineering Work Request

IEN

Inspection & Enforcement Information Notice

LCO

Limiting Condition for Operation

MST

Maintenance Surveillance Test

NRC

Nuclear Regulatory Commission

OEF

Operational Experience Feedback

ONS

Onsite Nuclear Safety

OST

Operations Surveillance Test

PH

Hydrigen ion concentration

PW

Primary Water

SI

Safety Injection

SRO

Senior Reactor Operator

SW

Service Water

TCV

Temperature Control Valve

TS

Technical Specification

UFSAR

Updated Final Safety Analysis Report

URI

Unresolved Item

VIO

Violation

WR/JO

Work Request/Job Order