ML20155A875

Insp Rept 50-395/88-17 on 880801-31.Violations Noted.Major Areas Inspected:Unresolved Items,Monthly Surveillance & Maint Observations,Operational Safety Verification,Esf Sys Walkdown & Onsite Followup of Events

ML20155A875
Person / Time
Site:	Summer
Issue date:	09/15/1988
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20155A851	List: ML20155A848 ML20155A862 ML20155A875
References
50-395-88-17, NUDOCS 8810060107
Download: ML20155A875 (8)

See also: IR 05000395/1988017

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/*  % UNITED STATES

3 .g NUCLEAR REGULAYORY COMMISSION

o * REGION 11

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[ 101 MARIETTA ST., N.W.

e . . , e *, AYLANTA GEORGIA 30323

Report No.: 50-395/88-17

Licensee: South Carolina Electric and Gas Company

Columbia, SC 29218

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

Facility Name: V. C. Summer

Inspection Conducted: August 1 - 31, 1988

Inspector': I

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/ Richard L. Prevatte Oate Signed

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perry C. Hopkins Date Signed

Accompanying Per nnelp Stevep J. Vias (August 22 - 26, 1988)

Approved by: 6' b d+v' - - _f TN

H6gh C.6 Dance, Sect n Chief 0 te igned

Division of Reactor Projects

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SUMMARY

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

'nspectors onsite, in the areas of unresolved items, monthly surveillance

observations, monthly maintenance observation, operational safety verification,

f engineered safety features system walkdown, onsite followup of events and

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subsequent written reports, action on previous inspection findings, design,

design changes and modifications, and other areas.

I Results: The licensee's periodic Jerformance of STP's has resulted in some

temporary procedure chanJes and procedure revisions. Review by procedure

writing groups appears to satisfy procedure resiew requirements. Too many

1 changes to a procedure without reprint and study by those who perform STP's

could load to confusion and/or errors by personnel who perform test procedures.

With tho upcoming outage scheduled for September 16, 1988, there appears to

have been considerable cooperative ef forts by the several discipline groups to

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produce an outtae schedule of significant detail.

Within the areas inspected, the following violation was identified:

- Failure to follow procedures, paragraph 8.

One unrosolved item was identified involving steam path yielding potential for

postulated steam breaks, paragraph 7a.

G810060107 080916

PDR ADOCK0500g5

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

• W. Baohr, Manager, Chemistry and Health Physics

K. Beale, Manager, Nuclear Protection Services

• 0. Bradham, Vice President, Nuclear Operations

C. Bowman, Manager, Scheduling and Modifications

M. Browne, General Manager, Station Support

W. Higgins, Supervisor, Regulatory Compliance

S. Hunt, Manager, Quality Systems

• A. Koon, Manager, Nuclear Licensing

• G. Moffatt, Manager, Maintenance Services

D. Moore, General Manager, Engineering Services

• K. Nettles, General Manager, Nuclear Safety

C. Price, Manager, Technical Oversite

J. Shepp, Associate Manager, Operations

• J. Skolds, General Manager, Nuclear Plant Operations

• G. Soult, General Manager, Operations and Maintenance

G. Taylor, Manager, Operations

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

• M. Williams, General Manager, Nuclear Services

K. Woodward, Manager, Nuclear Operations Education and Training

NRC Resident Inspectors

• P. Hopkins, Resident Inspector

R. Prevatte, Senior Resident Inspector

S. Vin , Project Manager

Other licensee employees contacted included engineers, technicians,

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

"Attended exit interview

Acronyms and initialisms used throughout this report are listed in the

last paragraph.

2. Unresolved Item **

See paragraph 7a for a unresolved item identified in this report.

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Unresolved items are matters about which more information is required to

determine whether they are acceptable or may involve violations or

deviations.

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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

13 selected surveillance tests including all aspects of the Steam

Generator "A" Steam Pressure (PT 474) Operability Test, (STP 303.005).

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.

During this inspection period, personnel in general, who performed the

surveillance procedures were knowledgeable and appeared to have

familiarized themselves with the procedures prior to the performance of a

particular surveillance procedure. Coordination and communications

between the several disciplines required to perform STP's were adequate.

Parts, components, test equipment or materials used by test personnel

during scheduled surveillance testing activities were found to be properly

documented on the associated implementing work requests and the STP's.

No violations or deviations were identified.

4. Monthly Maintenance Observation (62703)

The inspectors observed mair.tenance activities of safety related systems

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 in whole or in part:

MWR 8901084 Investigate and repair steam generator "A" feedwater

regulator valve

PMTS P0109921 SWS "B" train flow operational testing

MWR 8801026 Repair switch on MCB for the high pressure turbine to the

main steam drain valve

PMTS 98203 Repair auxiliary building motor control center switchgear

room cooling fan motor (XFN0132-M0)

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PMTS 102296 Repair relief damper equipment in room 435 (XDP0234A)

PMTS 102276 Inspect and repair control room vent control damper

(XDP0021A)

PMTS 102292 Repair equipment area relief air damper (XDP0133A)

PMTS 105581 Repair and calibrate circuit breaker feeder for heat

tracing (XPC2009)

PMTS 108702 Inspect and replace spare feeder breaker (X5W1DA2)

MWR 8810218 Repair flat washers on intermediate range instrument drawer

KWR 8700053 Repair spool piece above support SFH0044 by replacing with

new gaskets

PMTS 103912 Check and repair spent fuel pit bridge crane

PMTS 103961 Lubricate spend feel pit bridge crane

PMTS 103963 Inspect spent fuel pit bridge crane for operation

KdR 8801249 Investigate and repair feedwater regulator valve (IFV00478)

MAR 88 WOO 37 Install RUSKA gauges on feedwater system to test for

moisture carry-over

KdR 20797005 Perform circuit termination for plant surveillance system

MWR 8800836 Repair fau'ty limit switch on loop "A" component cooling

pump "C"

Through observation and research conducted during this inspection it has

been determined that maintenance activities have been performed per work

request instructions and applicable procedures.

No violations or deviations were identified.

5. 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,

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

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equipment, the control of maintenance and surveillance activities in

progress, the implementation of radiatinn protective controls and the

physical security plan. Tours were conducted during normal and random off

hour periods.

In general, the operating crews were observed to be making good use of

their time, when not occupied with the normal operating routine. They

were observed making needed procedure changes, reviewing procedures, and

conducting on-the-job training for those standing watch under instruction.

Operations watch standing activities and the composition of control room

logs was being accomplished in Accordance with the requirements of the

controlling procedures and directives.

No violations or deviations were identified.

6. ESF System Walkdown (71710)

The inspectors verified the operability of an engineered safety features

(ESF) system by performing a walkdown of the accessible portions of the

Component Cooling Water System. The inspectnrs 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 thit valves, including

instrumentation isolation valves, were in proper position, power was

available, and valves were locked as appropriate. The inspectors compared

both local and remote position indications.

Several deficiencies were identified, such as equipment tags missing, oil

leaking from limitorques and valves needing some type of preservation.

Responsiveness by operations to these items was prompt and positive.

No violatiors or deviations were identified.

7. Onsite Followup of Events and Subsequent Written Reports (92700, 93702)

a. On June 7,1988, with the plant in mode 3 the licensee was notified

by the architect engineer for V. C. Summer Nuclear Station that a

design defect may yield the potential for steam propagation, which

could affect the safe shutdown of the plant under certain postulated

steam events. Direct steam paths through floor penetrations and more

tortuous propagational paths were identified. Upon verification of

the potential problem the licensee changed operational modes from

mode 3 to mode 4 The licensee opened several interior plant doors

to allow for the relief of pressure build-ups. One door was sealed

to prevent moisture intrusion in the event of the postulated steam

break.

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The licensee is performing further evaluations of this potential

problem to insure that adequate corrective actions are in place for

short and long term operations. For furthee information see LER

88-008, dated July 7, 1988. This is an unresolved item, steam line

rupture with potential to affect safe shutdown, 88-17-02.

b. The inspectors reviewed the following. LER's and SPR's to ascertain

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

identified event or deficiency was in conformance with regulatory

requirements, TS, license conditions, and licensee procedures and

controls. Based upon this review the following items are closed.

LER 87-11 Lots of 7.2 kV switchgear due to degraded voltage

SPR 88-006 Failure of diesel fire pump to start on valid test

signal

SPR 86-011 keeperability of the meteorological ir.strumentation

No vinlations or deviations were identified.

8. Action on Previous Inspection Findings (92701, 92702)

The inspectors further reviewed the July 26, 1988 reactor trip from 100*;

power, while SSPS was being tested. Subsequent to the June 1, 1988

reactor trip, while performing an SSPS logic test, the licensee made

changes to STP 345.074, SSPS actuations logic and master relay test, for

train "B", to insure that the breaker would be closed locally instead of

from the MCB. Personnel failed to follow the procedure in that the

breaker was closed from the MCB inst ad of locally at the RTB as

specified. The solid state protection system actuation logic and master

relay test for train B, STP 345.074, was initiated and channel "B" was

placed in test at approximately 9:00 a.m., on July 26, 1988. A reactor

trip occurred at 9:24 a.m. At approximately 4:30 p.m. , a relief shif t

supervisor entered the control room and discovered that SSPS train "B" was

still in test. The channel was returned to normal at approximately

5:30 p.m. STP 345.074, precaution step 3.9 limits the time that a

channel may be bypassed for testing to two hours. The procedure was not

followed in that operations allowed the SSPS train "B" to remain in bypass

for over eight hours. During the time "B" train was in test no protection

signal could have been generated by that channel. Step 3.10 of the above

procedure also requires that if the test was terminated prior to

ompletion it must be returned to normal. This is an additional example of

the above violation for failure to follow procedures, 88-17-01. See. Report

No. 50-395/88-14 and LER 88-009 for further information,

9. Design, Design Changes and Modifications (37700)

The inspectors reviewed four design changes,1.'sted belnw not previously

approved by NRR, to assure that the changes had been reviewed and approved

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in accordance with the Technical Specifications (TS) and 10 CFR 50.59.

During the review, the inspectors verified (1) that the design changes ,

were reviewed and approved in accordance with TS and established QA/QC

controls, (2) that design changes were controlled by established

procedures, (3) that the licensee conducted a review and evaluation of

test results and that these test results were within previously

established acceptance criteria and that any test deviations tere resolved

and necessary retesting was accomplished as appropriate, (4) that

operating procedure modifications were made and approved in accordance i

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with TS, and (5) that as-built drawings were changed to reflect the

modifications. The inspectors ot> served (1) that change activities were

conducted in accordance with the appropriate specifications, drawings, and

other requirements, (2) that acceptance and startup testing of modifi-

cations were conducted in accordance with technically adequate and

approved procedures, and (3) that appropriate controls were implemented,

(e.g. , firewatch, portable fire fighting equipment, welding and cutting

permit, etc.). Additionally, the inspectors reviewed the outstanding

facility change requests (FCR's) and determined that an excessive backlog

was not developing. Design changes reviewed were:

M F 21097 Installed spare pump concept for swing systems

No violations or deviations were identified.

10. Other Areas

Other activities related to the inspection program are noted:  ;

a. The Assistant Director for Region II Reactnr Projects, the Director,

Reactor Projects Directorate 11-1 and the Region II Deputy Director i

for Reactor Projects, visited and toured the plant NTC and EOF on

August 3, 1988.

b. The Senior Resident Inspector assisted Region II in conducting an OPA

of the Vogtle Nuclear Plant during the week of August 8 and d , 198S.

c. The Regional Project Engineer for V. C. Sumner assisted the Resident f

Inspectors during the week of August 22, 1988.

11. Exit Interview (30703)

The inspectirn scope and findings were summarized on August 31, 1988, with  !

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

the areas inspected and discussed the inspection findings. No dissenting ,

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comments were received from the licensee. The licensee did not identify

as proprietary any of the ' materials provided to or reviewed by the

inspectors during the inspection.

Item Number Description and Reference

88-17-01 Violation - Failure to Follow Procedures,

paragraph 8.

88-17-02 URI - Steam Line Rupture with Potential to  !

Affect Safe Shutdown, paragraph 7.

12. Acrenyms and Initialisms

EOF Emergency Operating Facility

ESF Engineered Safety Feature

LER Licensee Event Report

MCB Main Control Board

MWR Maintenance Work Request

NRC Nuclear Regulatory Commission

NRR Nuclear Reactor Regulation

NTC Nuclear Training Center

OPA Operational Performance Assessment

PMTS Preventative Maintenance Task Sheet

QA Quality Assurance

RTB Reactor Trip Breaker

SPR Special Procedures Report

SSPS Solid State Protection System

STP Surveillance Test Procedures

SWS Service Water System

TS Technical Specifications

URI Unresolved Item

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