Text

Insp Repts 50-413/85-20 & 50-414/85-16 on 850426-0525. Violation Noted:Failure to Maintain Cleanliness Control in Diesel Generator Room.Deviation Noted:Failure to Meet Commitment to Remove Teflon Tape
	ML20133E925
Person / Time
Site:	Catawba
Issue date:	07/11/1985
From:	Dance H, Skinner P, Van Doorn P; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20133E873	List: ML20133E870; ML20133E887; ML20133E898; ML20133E925;
References
	50-413-85-20, 50-414-85-16, IEIN-85-15, NUDOCS 8508080066
	Download: ML20133E925 (9)
	v • d • e

1

.

e

'

UNITED STATES

[ PEE; #

o NUCLEAR REGULATORY COMMISSION

-

["

g

n REGION 11

j 101 MARIETTA STREET.N.W.

'f ATLANTA. GEORGI A 30323

%...../

Report Nos.: 50-413/85-20 and 50-414/85-16

Licensee: Duke Power Company

422 South Church Street

Charlotte, NC 28242

Docket Nos.: 50-413 and 50-414 License Nos.: NPF-35 and CPPR-117

Facility Name: Catawba 1 and 2

Inspection Conducted: 'l 26 - May 25, 1985

Inspectors: , -

P. H. ' 5kfhner - ~

ja_M a. /w

' jV ~

[8

Date Si(gned

s 2DKs /s - l0 W

Drte Signed

P. K. Tali Doorn' [ /g- a

Approved by: C W

H. C. Dan'ce, Section Chief

7!//!6

Ddte ' Signed

Division of Reactor Projects

,

SUMMARY

Scope: This routine, unannounced inspection entailed 210 inspector-hours on site

in the areas of site tours (Units 1 and 2); followup of licensee and NRC

identified items (Units 1 and 2); review of nonconforrping item documentation

(Unit 2); followup of IE Information Notices (Units 1 and 2); Instrumentation

(components and systems) - observation of work (Units 1 and 2); comparison of

as-built plant to FSAR description (Unit 2); maintenance observations (Unit 1);

surveillance observations (Unit 1); review of non-routine event reports (Unit 1);

and plant operations review (Unit 1).

l

l Results: Of the 10 areas inspected, no violations or deviations' were identified

in 8 areas; one apparent violation was found in one area - (Failure to maintain

cleanliness control in the diesel generator room paragraph 5.c.), and one

'

apparent deviation was found in one area (Failure to meet commitment to remove

teflon tape paragraph 3.d.).

"

85080B0066

DR 850712

ADOCK 05000413

l PDR

.

1

l

-

.

-

. ,

REPORT DETAILS

1. Persons Contacted

Licensee Employees

J. W. Hampton, Station Manager

E. M. Couch, Project Manager

B. F. Caldwell, Station Services Superintendent

W. M. Carwile, Test Director

J. W. Cox, Superintendent, Techncial Services

T. E. Crawford, Operations Engineer

L. R. Davison, Project QA Manager

C. W. Graves, Jr., Superintendent, Operations

C. L. Hartzell, Licensing and Projects Engineer

R. D. Hellams, Engineer-Turnover

C. S. Kelly, Instrumentation / Electrical Technial Support

R. A. Jones, Test Engineer

J.'A. Kammer, Test Director

P. G. Leroy, Licensing Engineer

T. D. Mills, Construction Engineer Electrical

E. B. Miller, QA Engineer

C. E. Muse; Operating Engineer

G. T. Smith, Superintendent, Maintenance

D.' Tower, Operations Engineer

Other licensee employees contacted included construction craftsmen,

technicians, operators, mechanics, security force members, and office

personnel.

Attended exit interview

2. Exit Interview

The inspection scope and findings were summarized on May 24, 1985, with

.those persons indicated in paragraph 1 above. The violation, deviation, and

unresolved items described in paragraphs 3.d. , 5.c. , 5.d. , and 8.b were

discussed in detail. The licensee acknowledged the findings and had no

dissenting comments.

The licensee did not identify as proprietary any of the materials provided

to or reviewed by the inspector during this inspection.

3. Licensee Action on Previous Enforcement Matters

a. (0 pen) Unresolved Item 413/84-87-03: Review of Operations Corrective

Action Program. The inspector met with the NCI/Non-Routine Event Task

Force Director and the Catawba Compliance Engineer to be updated on the

licensee efforts to address this item. A problem Investigation Report

System has been proposed and has been forwarded to appropriate licensee

r T

. .

.

'

.

. 2

personnel for comment. The inspector reviewed the proposed Station

Directives and PIR Flow Charts and considers the licensee to be making

satisfactory progress relative to this item. This item remains open

pending further review and implementation of the improved program.

b. (Closed) Violation 413/84-106-03: Failure to meet Technical Speci-

fication (TS) Requirements for Ice Condenser Doors Prior to Changing

Modes. The response for this item was submitted on March 29, 1985.

The inspector reviewed and verified implementation of corrective

actions described in the response and considers licensee actions to be

acceptable,

c. (Closed) Violation 413/84-106-04: Failure to Meet Procedure Require-

ments For Verification of Operability of the Ice Condenser. The

response for this item was submitted on March 29, 1985. The inspector

reviewed and verified implementation of corrective actions described in

the response and considers licensee actions to be acceptable.

d. (0 pen) Violation 413/84-104-01: Failure to Control Use of Teflon Tape.

The response for this item was submitted on January 24, 1985 and

March 14, 1985. In the response dated January 24, under Response to

Part (B) item 5, Duke Power Company states in part that the tape

installed by Nuclear Production in the Auxiliary Building will be

removed by March 1,1985. The inspector toured the Auxiliary Building

on May 7 and noted several examples where teflon tape was still

installed on system components which could possibly come in contact

with reactor coolant. This is a deviation 413/85-20-02: Failure to

Meet Commitment to Remove Teflon Tape.

4. Unresolved Items

New unresolved items are identified in paragraphs 5.d. and 8.b.

5. Independent Inspection Effort (92706) (71302) (Units 1 and 2)

a. The inspectors conducted tours of various plant areas. During these

tours, various plant conditions and activities were observed to

determine that they were being performed in accordance with applicable

requirements and procedures. No significant problems were identified

during these tours and the various evolutions observed were being

performed in accordance with applicable procedures.

During Unit 2 site tours, the inspector cbserved protection / storage of

plant equipment such as electrical cables, electrical components,

reactor vessel, reactor vessel internals, and safety-related

components,

b. The inspector reviewed Nonconforming Item Reports (NCIs) and corrective

action evaluations (R6As) to determine if appropriate documentation and

evaluations were being made.

._ _

- .

.

'

.

3

c. During a tour of the diesel generator room 1B on May 9,1985, the

inspector noted that the . room was not being maintained in the

cleanliness condition specified by Station Directive 3.11.1, House-

keeping and Cleanliness Levels In Safety Related Areas, Revision 9.

This cleanliness condition is specified as a Level IV area which

specifies all dirt and debris will be removed from the area. At the

time of the tour, this room had open buckets of oil, oily rags and

material, a portable filter assembly which had leaked onto the floor

and other accumulation of material that was not appropriate to this

area. This accumulation of material and debris in addition to being a

cleanliness problem, was also a fire hazard. The shift supervisor was

notified of this problem and took prompt action to reestablish

cleanliness requirements. This finding is a Violation 413/84-20-03:

Failure to maintain cleanliness control in the diesel generator room.

d. During the period of May 9,1985 to May 15,1985, Catawba experienced

nine actuations of Engir.eered Safety Features (ESF) systems or portions

thereof. Four of these actuations were associated with steam generator

low low level circuitry and five were associated with low low level

circuitry of the Nuclear Service Water System (RN). Preliminary

investigation by the inspector indicates that several of these

actuations were due to improper planning and communication. This item

will be identified as Unresolved Item 413/85-20-04: Multiple

Inadvertant Actuation of . ESF, pending additional review by the

inspector of these incidents and review of investigations conducted by

plant personnel.

No violations or deviations were identified.

6. Licensee Identified Items 50.55(e) (99020) (Units 1 and 2)

a. (Closed) CDR 414/84-05: Damaged Diesel Generator Oil Seals and Turbo

Charger Thrust Bearings. Reports for this item were submitted on

April 26,1984 and July 5, 1984. The inspector reviewed these reports

and verified implementation of corrective actions identified in the

reports and considers licensee actions to be acceptable.

b. (Closed) CDR 413, 414/84-08: No Circuit Protection Provided for Two DC

Welding Circuits. Reports for this item were submitted on May 10, 1984

and March 1, 1985. The inspector reviewed these reports and verified

implementation of corrective actions identified in the reports and

considers licensee actions to be acceptable.

c (Closed) CDR 414/84-10: Rotork Actuators Fitted with Undersized Set

Screws. Reports for this item were submitted on May 16, 1984;

August 30, 1984; February 1,1985 and April 1,1985. The inspector

reviewed these reports and verified implementation of corrective

actions identified in the reports and considers licensee actions to be

acceptable.

!

h

!

E

"

-

T

.

'

.

,

. 4

s

d. (0 pen) CDR 414/85-02: Vendor Weld on SI Accumulator Tank-Rejectable

Radiographic Indications. The inspector observed repair welding of the

shell to upper head weld of Accumulator 20. Control of Welding and

non-destructive examination appeared to be adequate. This item remains

open pending completion of repair welding and radiography.

e. (Closed) CDR 414/85-04: Stainless Steel Valves Welded with Carbon

Steel Filler Material. The report for this item was submitted on

April 19, 1985. The inspector reviewed this report and verified imple-

mentation of corrective actions identified in the report and considers

licensee actions to be acceptable.

f. (0 pen) CDR 414/85-06: Overpressurization and Rupture of Volume Control

Tank During Cold Hydrostatic Testing. The inspector observed welding

in progress of the new Volume Control Tank being accompished by the

vendor (RECO). This including review of welding procedures, review of

licensee surveillance of the vendor and visual inspection of fitup and

selected welds. This item remains open pending completion of the

repair work and completion of further evaluations being conducted by

the licensee.

No violations or deviations were identified.

7. Followup of IE Information Notices (92717) (Units 1 and 2)

The inspector verified that the licensee had reviewed and taken appropriate

corrective actions relative to Information Notice 85-15: Nonconforming

Structural Steel for Safety,-Related Use. The licensee evaluated the one

shipment received from the vendor to be acceptable for its use in the Unit 2

Turbine Building.

No violations or deviations were identified.

8. Instrumentation (Components and Systems) - Observation of Work and Work

Activities (52153) (Units 1 and 2)

a. Requirements for installation of instrumentation are contained in

various licensee specifications and site procedures. The inspector

observed installed instrumentation for conformance to requirements in

the areas of location, conformance to installation procedure require-

ments, use of specified materials and components, mounting of

instruments, routing of tubing, tubing supports, inspection,

separation, physical protection and record keeping. The inspector also

reviewed instrumentation Departmental Audit No. CD-84-16 dated

December 28, 1984. The instrument loops observed were process control

loops 2KC PG 7980 (Component Cooling Pump Motc r Cooler) and 2CAPG5020

(Auxiliary Feedwater Pump A Suction Pressure); ESF loops 2NSPT 5040 and

2NSPT 5380 (Contaiment Pressure); and safety-related display and safe

shutdown loops 2FWLT5120 (Refueling Water Storage Tank Level) and 2NILT

5260 (Containment Sump Level).

m

.

..

3

'

.. - , .

t 5

b. During. this review, . questions arose which were unable to be fully

addressed prior to the 'end of the inspection period. These questions

-inv'olve loop 2FWLT5120 and involve additional verification required of

the inspector and evaluations required by the licensee. These

-questions are as follows:

(1) Verification that insulators and heat tracing personnel are

+ adequately trained to prevent damage to safety-related instrument

tubing. This verification is required since this work is

conducted after. construction inspections are complete. 1

(2) ~ Verification that insulation does not prevent expansion loops from

functioning properly.

-(3) Verification that instruments mounted in electrical boxes are

seismically mounted and properly inspected. There appeared to be

some confusion as to. inspection requirements for mounting of these

types of instruments.

(4): During review of the inspectors questions the licensee noted that

.a change to the instrument inspection instruction (M610) had

inadvertantly deleted inspection of mounting. The licensee

indicated that a preliminary evaluation indicated that mounting

-

had been inspected anyway. This must be verified and the

instruction must be corrected.

(5) Loop 2FWLT5120 does not appear to-meet minimum slope criteria at-

the expansion loop. Inspection of similar loops in Unit 1

disclosed possible slope violations in loops 1FWLT 5000, 5010 and

,

5120. The licensee was requested to evaluate this problem as to

significance and cause.

(6) During inspection of Unit 1 loops it was noted that heat traced

loop 1FWLT5000 was not insulated. The licensee was requested to

evaluate this condition.

These questions are assigned Unresolved Item No. 413/85-20-01,

414/85-16-01: Verification of Adequate Installation of Instrumen-

'tation.

No violations or deviations were identified.

9. -Comparison of As-Built Plant to FSAR Description (37301) (Unit 2)

-The inspector verified that control and logic instrumentation met the FSAR

. description for Train A of the Residual Heat Removal System.

No violations or deviations were identified.

!

y

,

T

-

.

, .

. 6

'

10. Maintenance Observations (62703) (Unit 1)

Station maintenance activities of selected systems and components were

observed / reviewed to ascertain that they were conducted in accordance with

the requirements. The inspectcr verified licensee conformance to the

requirements in the following areas of inspection: (1) that the activities

were accomplished using approved procedures, and functional testing and/or

calibrations were performed prior to returning components or systems to

service; (2) quality control records were maintained; (3) that the

activities performed were accomplished by qualified personnel; and (4) parts

and materials used were properly certified. Work requests were reviewed to

determine status of outstanding jobs and to assure that priority is assigned

to safety-related equipment maintenance which may affect system performance.

Examples of this observation was work performed to correct seat leakage of

valves 1XC 50A, 1KC 53, and 1KC 995.

No violations or deviations were identified.

11. Surveillance Observations (61726) (Unit 1)

During the inspection period, the inspector verified plant operations were

in compliance with various TS requirements. Typical of these requirements

were confirmation of compliance with the TS for reactor coolant chemistry,

refueling water tank, residual heat removal, control room ventilation, and

DC electrical power sources. The inspector verified that surveillance

testing was performed in accordance with approved written procedures, test

instrumentation was calibrated, limiting conditions for operation were met,

appropriate removal and restoration of the affected equipment was

accomplished, test results met requirements and were reviewed by personnel

other than the individual directing the test, and that any deficiencies

identified during the testing were properly reviewed and resolved by

appropriate management personnel.

Typical of the surveillance items that were witnessed in part or in full

were weighing of high pressure carbon dioxide cylinders,125 VOC Essential

Diesel Auxiliary Power System Battery Service Test, and various calibrations

of portions of the nuclear instrumentation and radiation monitoring systems.

No violations or deviations were identified.

12. Review of Licensee Nonroutine Event Reports (92700) (Unit 1)

The below listed Licensee Event Reports (LERs) were reviewed to determine if

the information provided met NRC requirements. The determination included:

adequacy of description, verification of compliance with TS and regulatory

requirements, corrective action taken, existence of potential generic

problems, reporting requirements satisfied, and the relative safety signifi-

cance of each event. Additional inplant reviews and discussion with plant

personnel, as appropriate, were conducted for those reports indicated by an

asterisk (*). The following LER's are closed:

_

a .-

.

-

.. ,

,

7

84-22* 11/15/84 Inoperable Emergency Core Cooling

Flowpath

84-23* 11/19/84 ESF Actuation-Auxiliary Feedwater

Pump Start Due To Trip Of Main

Feedwater Pump

84-24* 11/24/84 Low-Low Steam Generator 1C Level

Actuation Of Motor Driven Auxiliary

Feedwater Pumps

84-25* 11/27/84 Auto Start Of Auxiliary Feedwater

Pumps On A Trip of Main Feedwater

Pumps

84-26 11/27/84 Required ~ Fire Watches Not Performed

84-28 12/5/84 ESF Acutation Due To Blackout on

Essential Switchgear

84-29* 12/6/84 Potential Loosening Of Control Rod

Drive Mechanism Set Screws

84-30 11/29/84 Containment Penetration Leak Rate

Test Improperly Performed

85-02* 12/31/84 Ice Condenser Lower Inlet Doors

Blocked Open

85-04* 1/14/85 Manual Trip Of Reactor Following

Loss Of Cooling Water To Reactor

Coolant Pumps Motors

85-06 1/20/85 Inadvertant Cooldown During Natural

Circulation Test

85-10 2/1/85 Power Range Instrumentation Neutron

Flux - High Negative Rate Trip

85-12 2/9/85 Safety Injection Caused By A Static

Inverter Failure

85-16 3/2/85 Incorrect Calibration Of Power Range

Trip Setpoints

85-20 3/14/85 Reactor Trip Caused By A Loose Power

Range Detector Cable

85-21* 3/13/85 Inoperable Turbine Driven Auxiliary

Feedwater Pump

l

,

. ,. -

-

.

_

. 8

85-23 3/29/85 Seventy-five Percent Power Exceeded

During Testing Prior To Authori-

zation

No violations or deviations were identified.

13. Plant Operations Review (Unit 1) (71707 and 71710)

The inspectors reviewed plant operations throughout the reporting p ariod to

veri fy conformance with regulatory requirements, TS and administrative

controls. Control room logs, danger tag log, TS Action Item Log, and the

removal and restoration log were routinely reviewed. Shift turnovers were

observed to verify that they were conducted in accordance with approved

procedures.

s

The inspectors also verified by observation and interviews, that measures

taken to assure the physical protection of the facility met current

requirements. Areas inspected included the security organization, the

establishment and maintenance of gates, doors, and isolation zones in the

proper condition, that access control and badging were proper, and

procedures followed.

In addition to the areas discussed above, the areas toured were observed for

fire prevention and protection activities. These included such things as

combustible material control, fire protection systems and materials, arid

fire protection associated with maintenance and construction activities.

During this inspection period the inspector reviewed the Auxiliary Shutdown

Panels instrumentation and controls againsy the controls listed in FSAR

Tables 7.4.7-1, 7.4.7-2, aqd 7.4. 7-3. A gcomparison of the listed

instruments actually installed on these panels shows that there are several

instruments and controls that do not agree with the instruments identified

in these tables. This was discussed with the licensee. The licensee

provided the inspector a proposed change in the FSAR (Revision 12) which

identifies some of the differences but this proposed change does not

identify all the differences. The licensee has stated that another revision

is being developed for submittal to the NRC for approval prior to fuel load

on Unit 2. Based on this discussion, this item is identified as an

Inspector Follow-up Item 413/85-20-05: Correction of FSAR Tables 7.4.7-1,

7.4.7-2, and 7.4.7-3.

No additional violations or deviations were identified.

14. Previously Identified Inspector Findings (92701) (Unit 1)

(Closed) Inspector Followup Item 413/84-79-02: Completion of Core Damage

Mitigation Training. The licensee committed to completion of core damage

mitigation training for applicable personnel by completion of full power

testing. The inspector reviewed the training and selected training records

of various personnel. Based on this review this item is closed.

l

ML20133E925

Text

Navigation menu

Search