ML20205G734

Insp Rept 50-395/86-13 on 860701-31.Violation Noted:Failure to Perform Timely Fire Watch Patrols

ML20205G734
Person / Time
Site:	Summer
Issue date:	08/07/1986
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20205G676	List: ML20205G671 ML20205G708 ML20205G734
References
50-395-86-13, NUDOCS 8608190608
Download: ML20205G734 (8)

See also: IR 05000395/1986013

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UNITED STATES l

/ g *[8709'o NUCLEAR REGULATORY COMMISSION

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o REGION 11

j 101 MARIETTA STREET.N.W.

• 't ATLANTA, GEORGIA 30323 -

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Report No. : 50-395/86-13

Licensee : South Carolina Electric and Gas Company

Columbia, SC 29218

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

Facility Name : V. C. Summer

InspectionConduc}e  : July 1 - 31, 1986

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Inspectors : - ez

Richa d L. Prev tte ' Date

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Pe Ct Hopkins Dat Si ned

Approved by : L MA( w E7gb

Hugh C/. Dance, Section Chief Date' Signed

Division of Reactor Projects

SUMMARY

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

on site in the areas of licensee action on previous enforcement matters, onsite

followup of events and subsequent written reports, monthly surveillance observa-

, tions, engineered safety features system walkoown, monthly maintenance observa-

tion and, operational safety verification.

Results: One violation was identified: Failure to perform timely fire watch patrols.

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PDR ADOCK 05000395 l

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REPORT DETAILS

1. Persons Contacted

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Licensee Employees

D. Nauman, Vice President, Nuclear Operations

0. Bradham, Director, Nuclear Plant Operations

J. Skolds, Deputy Director, Operations and Maintenance

K. Woodward, 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

M. Williams, Manager, Nuclear Education and Training

L. Blue, Manager, Support Services

S. Hunt, Manager, Quality Assurance Surveillance Systems

W. Higgins, Associate Manager, Regulatory Compliance

J. Sefick, Manager, Nuclear Security

B. Williams, Supervisor, Operations

L. Safely, Fire Protection

Other licensee employees contacted included engineers, technicians,

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

2. Exit Interview (30702, 30703)

I The inspection scope and findings were summarized on August 1,1986, with

j those persons indicated in paragraph 1 above. The inspectors described the

areas inspected and discussed the inspection findings. The licensee did not

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

, the inspectors during the inspection. One violation was identified. The

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licensee noted that corrective action had been implemented to preclude

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recurrence of this violation.

3. Licensee Action on Previous Enforcement Matters (92702)

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(Closed) Violation 85-34-02, Missing Jumpers in OPDT Circuits Allowed -

Trip Setpoint to Vary in Non-Conservative Direction on Decreasing Tave. The

licensee provided a written response to this violation in a letter to

Region II, dated February 5,1986. The inspector reviewed this response y

and found it to be satisfactory. The jumpers were installed and tested

successfully. Procedures STP 345-001, STP 345-002, and STP 345.003 were

revised to address this item. The licensees action appears to be adequate.

This item is closed.

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(Closed) Violation 86-07-01, Inadequate Cable Tray Thermo-lag 'Installa-

tion. The licensee provided a written response to this violation in a

letter to Region II dated May 2, 1986. The inspector reviewed the

licensee's response and procedural changes implemented by the licensee to

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prevent recurrence of this item. The additional controls delineated in

Nuclear Quality Control Inspection Procedure (A-NQCP-5) and Station

Administrative Procedure, Design Control / Implementation and Engineering

Interface (SAP-133), appear adequate to prevent recurrence. A reinspection

of portions of the installation revealed that the installation deficiencies

have been corrected. This item is closed.

(Closed) Potential Generic Item 86-04, Diesel Generator Field Flash

Circuits for Morrison-Knudson Diesels. The deficiency as described in the

above item is not applicable to the V. C. Summer Nuclear Station Diesels.

This item is closed.

(Closed) Potential Generic Item 85-06, Conax Seal Body Sub-assemblies.

Only two Conax electric conductor seal assemblies are installed 'for the IC

thermocouple up grade and they are of a different design. This item is

closed.

(Closed) Unresolved Item 85-34-03, Reactor Building Spray Pump Strainers.

Reference letter dated May 7, 1986, to Mr. A. F. Gibson, Region II from

Mr. D. G. McDonnald, NRC, Subject: Construction strainers in containment

spray system at V. C. Summer, and the safety evaluation attached thereto

addresses the concerns raised on system operability with the strainers

installed. The strainers have been removed. This item is closed.

(Closed) Inspector Follow-Up Item 83-27-05, Operational Quality Assurance

Plan Requirements. This item addressed a concern for ambiguity in quality

assurance plans whereas the term " Calibration Standards" was not consistent

with other " Standards" in the documents. The criteria, standards and other

unclear language has been corrected in the revised Quality Assurance Plan

and through issuance of a Nuclear Quality Control Plan for Equipment

Control. The materials inspected appear to be adequate for reasonable

understanding and clarification. This item is closed.

(Closed) Inspector Follow-up Item 82-54-02, Leak Detection Auxiliary

Building Sump / Floor Drain Level Hi-Alarms. The electrode probe of the level

element in the auxiliary building sump was modified to indicate the proper

level. This item is closed.

(Closed) Unresolved Item 85-46-01, Pressurizer Spray Valve Failure. The

actions taken by the licensee as reviewed by the inspectors appears to have

been adequate. This item is closed.

4. Monthly Surveillance Observation (61726)

The inspectors observed surveillance activities of safety-related systems

and components to ascertain that these activities were conducted- in

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accordance with license requirements. The inspectors observed portions of

! selected surveillance tests including all aspects of one major surveillance

test involving safety-related systems. The inspectors also verified that

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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 TS

requirements, that test discrepancies were rectified, and that the systems

were properly returned to service. The following specific surveillance

activities were observed:

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STP 102-002 NIS Power Range Heat Balance

STP 112-002 Reactor Building Spray Pump Test

STP 123-002 Service Water Pump "B" Operational Test

GTP 702 Verification of "B" Olesel Generator Operability

STP 120-001 Emergency Feed Water Pump "B" Test

STP 128-043 Ccatrol Building Elevation 448' Fire Barrier Inspection

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STP 114-001 Operational Leakage to Reactor Coolant Pump Seals

STP 105-007 Accumulator Isolation Valve Verification Test

STP 114-002 Operational Leak Test

STP 108-001 Quadrant Power Tilt Ratio

STP 124.001 Electrical Power System Weekly Test

STP 128.001 Electric Fire Pump Weekly Test

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STP 128.004 Diesel Fire Pump Weekly Test

STP 125.002 Diesel Generator "B" Operability Test

STP 391-009 Reactor Building Foundation Mat Triaxial Responser-

Sprectrum Recorder Operational Test

STP 302-003 Delta T-Tavg Frotection Loop 3 Operational Test

STP 125.002 Diesel Generator "A" Operational Test

STP 115.032 Reactor Building Air Lock Door Seal. Leak Test ,

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No violations or deviations were identified.

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5. Monthly Maintenance Observation (62703)

The inspectors observed maintenance activities of safety-related systems and

components to ascertain that these activities were conducted in accordance

with approved procedures, Technical Specifications (TS) and appropriate

industry codes and standards. The inspectors also determined that the

procedures used were adequate to control the act'.vity, 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

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activities were observed:

MWR 86C0100 Repair-Replace Mixed Bed Boric Acid Sample Valve,

XVD05774RDW

PMTS P0074115 Turbine Room Sump Pump "A"

MWR 86C0108 Repair Sterile Water System Pump, XPP0067

MWR 86C0073 Repair Radiochemistry Laboratory Sink Strainer-Drain Line

MWR 86M008 Replace Filter on the Waste Monitor Tank

MWR 86M003 Replace Filter on Waste Evaporator Feed Line

MWR 86M002 Replace Filter on the Hot Laundry-Hot Shower Tank

MWR 8601068 Adjust Air Supply Regulators to a Steam Generator IFU 3536

MWR 86Q0028 Replace Washer On Installed Bolt on Diesel Generator

MWR 86Q0312 Replace Washer, Clip and Bolt on Diesel Generator Door

MWR 86E005 Test and Repair of Emergency Lighting

MWR 8600801 Repair Standby Accumulator Pressure Gauge

MWR 8600895 Repair Steam Generator Feed Flow Instrument

MWR 8600582 Repair Valve on Recycle Evaporator

MWR 20350028 Install Computer Controllers

MWR 86C0085 Replace Flow Indicator Covers

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MWR 85E0317 Replace Torque Switch and Finger Base on Valve XVB09524A-CC,

Component Cooling Water

MWR 8600745 Repair Diesel Generator Rocker Arm Filter Leak '

MWR 8600879 Repair Accumulator Gauge

MWR 8600949 Repair Feedwater Gauge for SG "B"

MWR 8600959 Replacement of Instruments on the Feed Water System

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; 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.

No violations or deviations were identified.

7. 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

service water, component cooling water and emergency lighting systems. 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

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

both local and remote position indications.

No violations or deviatinns were identified.

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

The inspectors reviewed the following Licensee Event Reports (LERs) and

Bulletins to ascertain whether the licensee's review, corrective action and

report of the identified event were in conformance with regulatory require-

ments, technical specifications, license conditions, and licensee procedures

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

LER 85-034 Reactor Trip With Safety Injection

LER 85-025 Overpower Delta Temperature  ;

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IEB 84-02 Failures of G.E. Type HFA Relays in use in Class IE Safety

Systems

No violations or deviations were identified.

9. Onsite Followup of Events at Operating Reactor (93702)

a. On July 17, 1986, with the plant in Mode 1, the licensee, while

reviewing fire watch records identified that several fire watch patrols

had been missed between the dates of June 26 and July 17, 1986. This

is contrary to the requirements of TS 3.7.10 which requires the

licensee to establish and maintain hourly fire watch patrols for

inoperable fire barriers. This incident is similar to deviation

i 395/85-26-17 and violation 86-06-02. This is a violation, Failure To

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Perform Hourly Fire Watch Patrols, (395/86-13-01).

The licensee took immediate action to correct this deficiency by

implementing disciplinary action against the affected individuals who

failed to perform their assigned tasks. The licensee is submitting an

Licensee Event Report (LER 86-013).

b. On July 14, 1986, at 12:22 p.m. , with the plant . operating at 100

percent power, the 115 kV (Normal) offsite power to BUS XSWIDA was

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lost. The loss of power was caused by the automatic stripping (Fault

Protection) of one of two 115 kV power sources at the Parr sub-station,

l while the other power source was deenergized for maintenance. The

115 kV line was restored within twenty minutes, but was kept out of

service until a cause of the failure could be determined. The alternate

offsite power source was maintained. Plant systems responded as

designed. The licensee will discuss these items further in LER 86-012.

c. While operating in Mode 1, at 90 percent reactor power, on July 27, 1986,

at 1:45 a.m., a turbine trip occurred followed by a reactor trip.

The turbine trip occurred while PTP 102.001, Turbine Valve Testing, was

being performed. During the testing of control valve number 4, as the

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valve traveled to closed position, the main turbine tripped on low

EHC pressure, followed by a reactor trip. All systems responded as

designed. No safety injection occurred. The cause of this event was

determined to be a loose adjustment in a pressure sensing switch.

Repairs were completed and the unit returned to power. The licensee

is submitting a Licensee Event Report (88-014).

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