ML20195K255

Insp Rept 50-395/88-13 on 880501-31.Violation Noted.Major Areas Inspected:Monthly Surveillance Observations,Monthly Maint Observation,Operational Safety Verification,Esf Walkdown,Design & Design Changes & Mod

ML20195K255
Person / Time
Site:	Summer
Issue date:	06/14/1988
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20195K241	List: ML20195K238 ML20195K255
References
50-395-88-13, NUDOCS 8806290376
Download: ML20195K255 (9)

See also: IR 05000395/1988013

Text

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UNITED STATES

0 e Arag% NUCLEAR REGULATORY COMMISSION

e f'1 R EGION 11

j I I, 101 MARIETTA STRE ET, N.W.

• i r g ATL ANTA, GEORGI A 30323

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Report No. : 50-395/88-13

Licensee: South Carolina Electric and Gas Company

Columbia, SC 29218

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

Facility Name: V. C. Summer

Inspection Condu. ted: ay 1-3 , 1988

Inspect Ps: m # ve^~' Y

RichardL.frevatte, , Date Signed

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Date Signed

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Approved by: 'S/- [

Hugh C. Dance, Section Chief

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Date Signed

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/gn Division of Reactor Projects

SUMMARY

Scope: This routine, announced inspection was conducted by the resident

inspectors onsite, in the areas of monthly surveillance observations, monthly

maintenance observation, operational safety verification, engineered safety

features system walkdown, design, design changes and modification and other

areas.

Results: One violation was identified, failure to meet limiting condition of

operation prior to mode changes.

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8806290376 880616

PDR ADOCK 05000395 l

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

• D. Nauman, Vice President, Nuclear Operations

• 0. Bradham, Director, Nuclear Plant Operations

D. Moore, General Manager, Engineering Services

M. Williams, deneral Manager, Nuclear Services

• K. Nettles, General Manager, Nuclear Safety

J. Skolds, General Manager, Station Operations

• M. Browne, General Manager, Station Support

G. Moffatt, Manager, Mainter.ance Services

• G. Soult, Manager, Operations

A. Koon, Manager, Nuclear Licensing

C. Bowman, Manager, Scheduling and Modifications

K. Woodward, Manager, Nuclear Operations Education and Training

W. Baehr, Manager, Chemistry and Health Physics

S. Hunt, Manager, Quality Systems

K. Beale, Manager, Nuclear Protection Services

C. Prica, Manager, Technical Oversite

D. Warner, Manager, Core Engineering and Nuclear Computer Services

J. Shepp, Associate Manager, Operations

• W. Higgins, Supervisor, Regulatory Compliance

NRC Resident Inspectors

• R. Prevatte, Senior Resident Inspector

• P. Hopkins, Resident Inspector

Other licensee employees contacted included engineers, technicians,

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

• Attended exit interview

2. Exit Interview (30703)

The inspection scope and findings were summarized on June 1,1988, with j

those persons indicated in paragraph 1 above. The inspectors described l

the areas inspected and discussed the inspection findings. The licensee l

acknowledged the violation described in paragraph 5.b. The licensee did .

not identify as proprietary any of the materials provided to or reviewed l

by the inspectors during the inspection.

Note: A list of abbreviations used in this report is contained in

paragraph 11.

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3. 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 26 selected surveillance tests including all aspects of the Diesel

Generator Operability Test, STP 125.002. The inspectors also verified

that required administrative approvals were obtained prior to initiating

the test, testing was accomplished by qualified personnel, required test

instrumentation was properly calibrated, data met TS requirements, test

discrepancies were rectified, and the systems were properly returned to

service.

No violations or deviations were identified.

4. Monthly Maintenance Observation (62703)

The inspectors observed maintenance activities of _ safety related systems

and componeras to ascertain that these activities were conducted in

accordance with approved procedures, TS and appropriate industry codes j

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 veri-

fied 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 I

activities were observed:

MWR 8600458 Repair bulb holder for the autostart indication on DG "B"

PMTS P010185 Inspect, clean, repair and check integrity of terminations I

in DG "B" control cubicle '

MWR 88G0041 Repair fire door barrier 103 east penetration

PMTS P100381 Tear down, inspect and repair operator for CCW supply

header valve XVB9524B-CC

PMTS P0103094 Inspect and repair motor starter for XVB95268-CC

MWR 8701488 Inspect and repair oil leak from bearing on CCW pump "C"

MWR 88G0081 Investigate and repair trouble alarm on smoke detector

system

MWR 87T0297 Perform east & west penetration access area temperature

test

MWR 8800399 Calibrate condensate makeup flow indicators

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MWR 88G0093 Repair smoke detectors

MWR 8810125 Verify and mark up drawing for environmental system

MWR 880446 Investigate and repair turbine switch gear cooling trouble

alarm

PMTS P0103347 Inspect and repair waste evaporator

PMTS P0098194 Inspect and repair heat shrink terminations en IDB air

handling unit supply fan motor

MWR 880678 Investigate and repair loose wires on diesel fire pump

start switch

MWR 213630026 Install cable in the turbine building and control building

FMTS P0102479 Calibrate service water flow indicator loop "B"

MWR 88G0115 Repair smoke detector IXA 4923A

MWR 8800679 Trouble shoot and repair the component cooling water "B"

pump flow problems

PMTS P0103570 Calibrate instrumentation on conductivity recorder

PMTS P0102480 Loop calibration for RCP "A" 1 seal water flow

(

PMTS P010272 Loop calibration for SG "B" supply header pressure

transmitter

MWR 8800682 Investigate and repair inverter XIT 5909

MWR 87M0532 Replace electrical thermo link on air handling unit

A(XF0021A)

MWR 87M0533 Replace electrical thermo link on air handling unit

B(XF0021B)

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PMTS P0094759 Perform electrical maintenance on SWP's "A",

"B", and "C"

PMTS P0094671 Perform maintenance on the transfer switches for

SWP's "A", "B", and "C"

MWR 88C0072 Inspect and repair leaks in main condenser

No violations or deviations were identified.

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5. Operational Safety Verification (71707)

a. 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, control room logs, tagout books, operating

orders, jumper / bypass controls, computer printouts and annunciators.

Tours of other plant areas were conducted to verify 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.

b. On May 12, 1988 at 4:46 a.m., the plant experienced a reactor trip

and SI from 100% power. The above resulted from full closure of

the MSIV 2801 "A" while performing the Main Steam Valve Operability

Test, STP 121.002. The closure of MSIV "A" caused the steam flow to

increase rapidly from SG "B" and "C". This resulted in a rapid

decrease in steam line pressure in steam lines "B" and "C" which

actuated the protection circuitry for low steamline pressure reactor

trip /SI. All systems, with the exception of service water flow to

the RBCU's, functioned as required.

The RBCU's are normally supplied with cooling water from the

industrial cooling water system, a non-safety grade system. On

receipt of a SI signal, the RBCU's are aligned to the SWS and

provided with cooling water boosted in pressure by the SWBP's. This

occurred immediately after the above trip and SI. However, the

required flow of 4000 GPM per train was never fully achieved and l

mair.tained on "A" or "B" train while the units operated on service l

water from approximately 4:54 a.m. until 5:34 a.m.

The above information is contained in the computer post trip review

printout. SAP 132, Off-normal Occurrence Evaluation, Reporting and

Resolution, required that this information be reviewed by the shif t l

engineer prior to plant restart. This information was reviewed by

the shift engineer however, the inadequate flow to the RBCU's was not

identified. On May 16, 1988 ISEG reviewed the computer printouts

(trip package) associated with the reactor trip and identified that

adequate flow had never been achieved by the RBCU's while operating

on service water. Both "A" and "B" trains were then declared inoper-

able on May 16, '.988, at 3:00 p.m. The "A" train units were retested

and restored to an operable status on May 17, 1988, at 1:30 p.m. The

"B" train units were returned to an operable status after chemical

cleaning on May 23, 1988, at 10:26 p.m. After completion of the

cleaning on "B" train the "A" train units were taken out of service

for a period of four days and chemically cleaned.

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After chemically cleaning both RBCU's, problems were again experi-

enced with RBCU's for train "B". This occurred when train "B" was

swapped from service water pump "B" to pump "C". After these pumps

were swapped flow decreased over a period of approximately four

hours from 4100 GPM to approximately 3900 GPM. At that time this

train was swapped back to pump "B". The flow was still below the TS

limit of 4000 GPM. At that time the valves associated with train "B"

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RBCU were cycled and flow on this train increased to slightly above

4000 GPM. During the cycling of valves a relief valve on the service

water cooling inside the reactor building lifted and failed to fully

reseat. An entry was made into the reactor building and the valve

was repaired.

The above problem resulted from what is believed to be infestation of

corbicula or iron oxide deposits in stagnant service water piping

between the SWBP's and the service water isolation valves for the

RBCU's. When the RBCU's were transferred to service water during the

safety injection, the corbicula or iron oxide deposits were swept

into the cooling units and plugged some of the small diameter tubing.

Since it was concluded that corbicula could be the cause of system

flow problems, commercial diving contractor services were obtained to

clean the service water intake structure bays. On May 28, 1988,

divers cleaned the service water intake structures and removed

approximately 15-20 gallons of small clams.

Both trains of RBCU were declared operable on May 28, 1988. Manage-

ment is currently analyzing data and evaluating how this system

will be operated and what testing will be needed to maintain this

system operable.

The failure of the reactor operator to identify the low flow from

SWBP "B" and the RBCU's coupled with the shif t supervisors and shif t

engineers failure to conduct a thorough post trip review resulted in

the unit beirg restarted on May 12, 1988, at 8:24 p.m. and returning

to power operation on May 13, 1988, at 00:21 a.m. Thit is contrary

to the requirement of TS 3.0.4 which requires that all limiting

conditions of operations be met prior to exiting Mode 3 and cntering

Mode 2 and Mode 1. This is a violation, failure to meet the limiting

condition of operation prior to mode changes, 88-13-01.

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c. On May 26, 1988, the licensee identified that circulating water tube

leaks existed in the "A" section of the main turbine condenser. A

decision was made to reduce the plant to 40 percent power and perform

the repairs with the unit on the line with one half of the condenser

isolated and drained. Power was reduced on May 28,1988 to 40

percent. The "A" section of the condenser was isolated and drained.

Two tube leaks in the high pressure and one in the low pressure

sections on "A" condenser were located and repaired. The unit was

returned to 100 percent power on May 30, 1988.

On May 31, 1988 the plant again experienced problems with circulating

water leakage in the main condenser. Power was reduced to

approximately 38 percent to reduce the effects of out of

specification chemistry. The licensee with the assistance of a

contractor located and isolated the leaks to the "B" section of the

main condenser. The plant is currently in the process of making

repairs. This item will be tracked by the resident inspectors until

completion. Additional details will be provided in the rext monthly

report.

One violation was identified as discussed in paragraph b. above.

6. ESFSystemWalkdown(71710)

The inspectors verified the operability of an ESF system by performing a

walkdown of the accessible portions of the Diesel Generator Fuel Oil

System. The inspectors confirmed that the licensee's system lineup

procedures matched plant drawings and the as-built configuration. The

inspectors looked for equipment conditions and items that might degrade

performance (hangers and supports were operable, housekeeping, etc.) and

inspected the interiors of electrical and instrumentation cabinets for

debris, loose material, jumpers, evidence of rodents, etc. The inspectors

verified that valves, including instrumentation isolation valves, were in

proper position, power was a /ailable, and valves were locked as

appropriate. The inspectors compared both local and remote position

indications. '

No violations or deviations were identified.

7. Design, Design Changes and Modifications (37700)

The inspectors reviewed design, design changes and modifications packages

initiated over the past two years. The areas reviewed were reactivity

control, instrumentation, reactor coolant system, emergency core cooling

system, containment systems, plant and electrical power systems, radwaste

and power conversion systems. A review of all modifications in the above

areas was cor. ducted. After this review the following five modifications

were selected for a detailed review and followup to insure that the design

changes were appropriately reviewed, approved and implemented in

accordance with TS and established quality assurance and quality control

procedures.

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a. Reactivity Control, MRF 20720 (open)

Installation of redundant PAMS class 1E neutron flux monitors

required by RG 1.97.

b. Emergency Core Coolino, MRF 21097 (completed)

This MRF provides changes, as necessary, to implement the "installed

spare" for swing pumps. The alignment both electrically and

mechanically of swing pumps had been incorrectly instituted in the

past due to confusion over interlocks.

c. Containment Systems, MRF 21022 (open), safety-related

Reduce RBCV minimum flow from 4000 GPM to 2000 GPM by changing the

RBCU service water discharge valves (XVG 3109 "A", "B", "C", and "D")

from passive to active valves during an accident,

d. Plant and Electrical Power Systems, MRF 20827 (completed)

Installation of single cell battery chargers with isolation fuses.

e. Radwaste Systems, MRF 20752 (open)

Installation of new portable demineralizers for processing liquid

radwaste.

This review is expected to be completed in June 1988 and will be reported

in the next resident monthly inspection report.

8. Other areas

The senior resident inspector spent the week of May 9-13, 1988, in NRR as

a participant in the NRR/ Region Il rotational exchange program. This

program is designed to improve communications, increase technical skills

and provide a better understanding of the job and responsibilities of the

NRR project manager.

9. List of Abbreviations

ARP Annunciator Response Procedures

CCW Component Cooling Water

DG Diesel Generator

DGF0S Diesel Generator Fuel >0il System

ESF Engineered Safety Feature

GPM Gallons Per Minute

ISEG Independent Safety Evaluation Group

LER Licensee Event Report

MRF Modification Request Form

MSIV Main Steam Isolation Valve

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MWR Maintenance Work Request

NRR Nuclear Reactor Regulation

PAMS Post Accident Monitoring System

PMTS Preventative Maintenance Task Sheet

RBCU Reactor Building Cooling Unit

RCP Reactor Coolant Pump

RG Regulatory Guide

SAP Station Administrative Procedure

SG Steam Generator

SI Safety Injection

SPR Special Procedures Report

STP Surveillance Test Procedures

SWBP Service Water Booster Pumps

SWP Service Water Pump

SWS Service Water System

TS Technical Specifications