ML20214M781

Insp Rept 50-395/87-11 on 870404-0504.Violations Noted: Failure to Verify That Steam Generator Tubes Properly Plugged

ML20214M781
Person / Time
Site:	Summer
Issue date:	05/15/1987
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214M768	List: ML20214M765 ML20214M769 ML20214M781
References
50-395-87-11, NUDOCS 8706010426
Download: ML20214M781 (8)

See also: IR 05000395/1987011

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. UNITED STATES

- [A Klotf o NUCLEAR REGULATORY COMMISSION

[ n REGION 18 ;

y ,j 101 MARIETTA STREET,N.W.

• I * ATLANTA, GEORGI A 30323

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Report No.: 50-395/87-11

Licensee: South Carolina Electric and Gas Company

Columbia, SC 29218

Docket No.: 50-395 License No.: NPF-12

Facility Name: V. C. Summer

Inspection Conducte : April 4 through May 4, 1987 ,

Inspectors: ( /1,%

Rfchard L. Pr patte

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Mate ' Signed

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Perry C. Hopkiris D6te Signed

Approved by: 0 ( At ( 7

Hugh C. Tance, Sec61on, Chief D6te Signed

Division of Reactor Projects

SUMMARY

Scope

This routine, announced inspection was conducted by the resident

l inspectors onsite, in the areas of licensee action on previous inspection

findings, onsite followup of events and subsequent written reports, monthly

surveillance observations, monthly maintenance observation, operational safety

verification, calibration, refueling activities, physical security and other

areas. .

Results: One violation was identified: Failure to verify that steam generator

tubes were properly plugged (Paragraph 9).

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

D. Nauman, Vice President, Nuclear Operations

0. Bradham, Director, Nuclear Plant Operations

J. Skolds, Deputy Director, Operations and Maintenance

G. Soult, Manager, Operations

M. Browne, Group Manager, Technical and Support Services

M. Quinton, Manager, Maintenance Services

A. Koon, Manager, Technical Support

G. Putt, Manager, Scheduling and Materials Management

K. Woodward, Manager, Nuclear. Education and Training

L. Blue, Manager, Support Services

S. Hunt, Manager, Quality Assurance Surveillance Systems

K. Beale, Manager Nuclear Protection Services

W. Higgins, Associate Manager, Regulatory Compliance

B. Williams, Supervisor, Operations

Other licensee employees contacted included engineers, technicians,

operators, mechanics, security force members, and office personnel.

2. Exit Interview (30702,30703)

The inspection scope and findings were summarized on May 4, 1987, with

those persons indicated in paragraph 1 above. The inspectors described

the areas inspected and discussed the inspection findings. The licensee

did not identify as proprietary any of the materials provided to or

reviewed by the inspectors during the inspection. One violation was

identified.

Violation 87-11-01, Failure to plug correct steam generator tubes. The

licensee offered no objections to the violation.

3. Licensee Action on Previous Inspection Findings (92701, 92702) j

(0 pen) Licensee Identified Item, 80-29-01, Charging pump minimum flow:

long term fix in progress, see SCE & G's letter to Denton, dated,

January 22, 1982. Report 87-08, paragraph 3, stated that the licensee

would submit a report to Nuclear Reactor Regulation (NRR) on the above.

The licensee submitted this information in a letter to NRR dated,

April 24, 1987. The office of NRR will review the response for adequacy.

This item remains open.

4. Monthly Surveillance Observation (61726)

The inspectors observed surveillance activities of safety related systems

and components to ascertain that these activities were conducted in

accordance with license requirements. The inspectors observed portions of

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selected surveillance tests listed below including all aspects of at

least one major surveillance test involving safety related systems. The

inspectors also verified that the required administrative approvals were

obtained prior to initiating the test, that the testing was accomplished

by qualified personnel, that required test instrumentation was properly

calibrated, that data met Technical Specification (TS) requirements, that

test discrepancies were rectified, and thot the systems were properly

returned to service. The following specific surveillance activities were

observed:

STP 115.033 Safety Injection / Chemical and Volume Control System

Valve Leak Test

STP 105.004 Residual Heat Removal Pump Test

STP 310.004 N.I.S. Intermediate Range (N-36) Calibration

STP 147.001 Reactor Building Penetration Test

STF 102.001 Source Range Analog Channel Operational Test (N-31, N-32)

STP 110.001 Pre-core Alterations Verification

STP 134.001 Shutdown Margin Calculation

STP 118.006 Reactor Building Purge and Exhaust Refueling Weekly Test

STP 401.002 Main Stream Line Code Safety Valves ASME Section XI Test

STP 150.012 Main Steam / Steam Generators Leak Test

STP 149.079 Service Water "B" Train Discharge Hydrostatic Test

STP 146.002 Reactor Makeup Water System Refueling Alignment

Verification

STP 125.004 Diesel Generator Load Rejection Test

STP 134.001 Shutdown Margin Calculation

i STP 128.004 Diesel Fire Pump Weekly Test

STP 115.020 Nuclear Drains System Valve Leakage Test

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STP 145.003 Gaseous Radwaste Treatment Ventilation Exhaust

Treatment Systems Operability Test

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STP 122.002 Component Cooling Pump Test

STP 125.002 Diesel Generator Operability Test

No violations or deviations were identified.

5. Monthly Maintenance Observation (62703)

The inspectors observed maintenance activities of safety related systems

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and components to ascertain that these activities were conducted in

accordance with approved procedures, TS and appropriate industry codes and

standards. The inspectors also determined that the procedures used were

adequate to control the activity, and that - these activities were

accomplished by qualified personnel. The- inspectors independently

verified that equipment was properly tested before being returned to

service. Additionally, the inspectors reviewed several outstanding job

orders to determine that the licensee was giving priority to safety

related maintenance and a backlog which might affect its performance was

not developing on a given system. The following specific maintenance

activities were observed:

MWR 21045007 Install new platform in the control room for the control

room supervisor

MWR 8700526 Repair leak on service water outlet expansion joint

MWR 8700547 Repair service water pipe IPX045068

MWR 8700528 Repair leak of socket weld where the line taps on to

the service water inlet piping to "B" chiller

MWR 32356003 Perform installation work and post modification testing

per MRF 32356 and MSI 32356-2, on chiller XHS0001B

MMP 300.012 Agastat replacement on chiller XHX00018

MWR 87T0099 Disassemble valve to reset nozzle ring settings on

XUS 02806HMS

MMP 290.002 Main steam safety relief valve maintenance and testing

No violations or deviations were identified.

6. Operational Safety Verification (71707)

The inspectors toured the control room, reviewed plant-logs, records and

held discussions with plant staff personnel to verify that the plant was

being operated safely and in conformance with applicable requirements.

Specific items inspected in the control room included: adequacy of

staffing and attentiveness of control room personnel; TS and procedural

adherence; operability of equipment and indicated control room status;

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control room logs, tagout books, operating orders, jumper / bypass

controls; computer printouts and annunciators. Tours of other plant areas

were conducted to veri fy equipment operability; control of ignition

sources and combustible materials; the condition of fire detection and

extinguishing equipment; the control of maintenance and surveillance

activities in progress; the implementation of radiation protective

controls and the physical security plan. Tours were conducted during

normal and random off hour periods.

No violations or deviations were identified.

7. Onsite Followup of Events and Subsequent Written Reports

(92700,93713,93702)

The inspectors reviewed the following Licensee Event Reports (LER's) to

ascertain whether the licensee's review, corrective action and report of

the identified event or deficiency was in conformance with regulatory

requirements, technical specifications, license conditions, and licensee

procedures and controls. Based upon this review the following items are

closed.

LER 85-008 Reactor trip failure of the secondary fuses

Three pressurizer safety valves were sent to Wyle Laboratories and one to

Crosby Valve and Gage Company in March, 1987, to veri fy proper set

points. On March 31, 1987, Wyle Laboratories notified the licensee that

the valves were tested and found that the as-found set points were outside

the technical specification limits of 2485 +/- 1% psig. Preliminary

analysis by the licensee indicates differences of as-set and as-found

set points to be a function of methods utilized to simulate in plant

environmental conditions. Further testing of the pressurizer safety

valves will be conducted by the licensee at hot plant onditions, using

the steam medium and a calibrated pressure assist device, with a test

method which simulates actual plant conditions. The licensee has reported

the event to the NRC in LER 87-05.

No violations or deviations were identOied

8. Calibration (56700)

The inspectors conducted a detailed review and evaluation of the

licensee's calibration program to determine its conformance with license

requirements, technical specifica', ions, licensee commitments and industry

guides and s'.andards. To accomp'ish the above, the inspectors completed

the following:

a. Conducted a review of licensee records and verified that the

calibration frequences of equipment met the requirements of technical

specifications.

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b. Reviewed a sample of 30 completed tests to establish that

documentation was complete; acceptance criteria had been met; approved

test procedures were used and the personnel conducting the tests were

qualified,

c. Examined the technical content of 13 surveillance test procedures for

adequacy.

d. Examined the technical content and adequacy of 10 instrumentation and

control maintenance procedures used to calibrate safety equipment

not addressed in technical specifications,

e. Reviewed the backlog of past due calibrations.

f. Observed and evaluated the performance of 2 components undergoing

calibration.

The results of the above indicate that the licensee's calibration program

has been properly implemented. Procedures are properly reviewed and

approved prior to implementation. Procedures contain steps that require

signatures after each item is completed; second verification of

critica steps is required; corrective action is taken and proper notifi-

cation is made when equipment is found out of calibration; test equipment

is identified and tracked; and limiting conditions for operators are

addressed. A review of the calibratior backlog indicates that management

is notified and action is taken on past due calibrations.

Based on this review it appears that the licensee's program is implemented

by adequate procedures, has adequate administrative controls, and is

staffed by trained and qualified personnel.

No violations or deviations were identified.

9. Refueling Activities (60710)

The inspectors continued to review the licensee's activities

associated with the current refueling outage which began on March 7, 1987.

The activities consisted of (1) testing of refueling equipment prior to

use, (2) the movement of fuel into the reactor core, (3) fuel inspection,

(4) drainage of the refueling canal, (5) reactor make up water system

refueling alignment verification and (6) reactor head replacement. The

inspectors verified that the periodic testing required by technical

specifications and station administrative procedures were completed within

the prescribed time limits.

The inspectors also observed the conclusion of work being performed on

the steam generators.

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On April 14, 1987, while performing maintenance and inspection, the

licensee discovered that two steam generator tube plugs had been installed

in the incorrect tubes in steam generator "C", cold leg. A review of this

item by the licensee, discovered that this problem had occurred in or

about November 21, 1985, during the second refueling outage. Further

review of the item revealed that after eddy current testing had determined

which tubes required plugging, a template had been designed and

constructed with drilled holes to match the tubes which required plugging.

In addition to the template holes drilled to allow tube plugging, two

pilot holes were drilled to attach a suspended tube plug basket. This

device performed adequately and the correct tubes were plugged on the hot

leg side. When the template was installed in the cold leg side of the

steam generator, the basket was not attached, and the Subsequent error

resulted in the plugs being installed through the template holes that would

have been used to suspend the tube plug basket. This deficiency was not

identified in the subsequent verification inspection. This failure to

identify this deficiency is contrary to the requirements of 10 CFR 50,

Appendix "B", Criterion X and the South Carolina Electric and Gas

Company's Operational Quality Assurance Plan that requires this is a

violation: Failure to plug correct steam generator tubes (87-11-01). The

licensee has corrected this deficiency and performed an analysis which

indicated that the incorrect plugging had no adverse effect on steam

generator operation. The licensee is currently evaluating plugging and

verification inspection procedures for steam generator tube plugging,

in order to strengthen the current procedures and methodology. The

licensee is preparing a LER on this subject.

Other than the above, no violations or deviations were identified.

10. Physical Security (71881)

The inspectors verified by observation, review of documentation of

records and personnel interviews that appropriate measures are taken to

assure the physical protection of the facility. The physical security

plan (PSP) provides adequate instructions to insure that the required

number of guards, search equipment and search procedures are in place.

Verification of adequate patrols, central control television monitors

and alarm stations are in place. Areas inspected included the

organization of the security force, the establishment of maintenance of

gates, doors and isolation zones. That access control and badging was

proper, that search practices were appropriate and that escorting and

communications procedures were followed.

The inspectors received an anonymous concern in regards to the lack of

management and supervision fulfillment of established security

procedures. A review of records, safeguards information, and storage of

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security records was performed, and in addition, interviews with

selected individuals and other random personnel, failed to support or

substantiate the concern. Unless there is more definitive information

forth coming. This item is considered closed.

No violations or deviations were identified.

11. Other Areas i

Senior resident and resident inspectors respectively, from the H.B.

Robinson plant visited V.C. Summer for orientation and familiarization

to fulfill requirements for onsite backup inspectors.

The Regional Administrator visited V.C. Summer and met with plant staff

on April 16, 1987. He participated in a reception and presented Nuclear

Regulatory Commission Senior Reactor Operator and Reactor Operator

Licensees to personnel who had recently completed the training and

examination program.

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