ML20215K329

Insp Rept 50-395/87-14 on 870505-31.Violations Noted:Failure to Promptly Evaluate & Classify Event & Inadequate Sys Operating Procedure for Svc Water Sys

ML20215K329
Person / Time
Site:	Summer
Issue date:	06/15/1987
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20215K277	List: IR 05000395/1987014 ML20215K275 ML20215K300 ML20215K329
References
50-395-87-14, NUDOCS 8706250293
Download: ML20215K329 (10)

See also: IR 05000395/1987014

Text

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Repopt No.: 50-395/87-14

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-Licensee: South Carolina Electric and Gas Company.

Columbia,.SC 29218

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Docket No.: .50-395 License No.: NPF-12 4

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Facility Name: V. C. Summer q

Inspection Conducted: May.5-31, 1987 .

Inspecto si

Richard L. Prevatte

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Perry C. opkins / Date Signed  !

Approved by: 64k b A '$ //

Date Signed

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Augh T. Dance, Section Chief

Division of. Reactor Projects

SUMMARY

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

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

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

surveillance observations, engineered safety features system walkdown, monthly

maintenance observation, operational safety verification, plant startup from ^

refueling and design, design changes and modifications. 1

Results: Two violations' or ' deviations were identified, Failure.. to promptly .

evaluate and classify an event and Inadequate system operating procedure for

the Service Water System.  !

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REPORT DETAILS

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1.. . Licensee Employees Contacted j

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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 Serv _ ices 1

Ac Koon, Manager, Technical Support 4

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'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. E..Beale, Manager Nuclear Protection Services

W. Higgins, Associate Manager, Regulatory Compliance

B. Williams, Supervisor, Operations

l Other licensee employees contacted included engineers, technicians,

operators,. mechanics, security f.orce members, and office personnel.

2. Exit interview (30702,30703)

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i The inspection scope and findings were summarized on June 1,1987, with  ;

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

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

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acknowledged the violations described in paragraph 6. The. licensee did

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

by the inspectors during the inspection.

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

(Closed) Inspector Followup Item 87-04-01, Contractor training records.

This item related to a concern associated with administrative errors in

individual training records and resumes for contractor personnel. It

additionally noted that the administrative procedures for Prime South had

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not been implemented. A reinspection of this area by the inspectors

indicated that the administrative procedures have been implemented and the

errors in individual training records and resumes have been corrected.

This item is closed.

(Closed) Unresolved Item 87-08-01, Access control to a vital area. This

item was followed up on in report 87-12, and identified as a violation.

This item, 87-08-01, is administratively closed and will be tracked as

violation 87-12-01.

(Closed) Inspector Followup Item 83-05-02, Liquid radwaste system

comments. This item of concern was associated with the system description

of the radwaste system in the FSAR and the implementation of Standard

Operating Procedures (SOP's), Liquid Waste Release Permits (LWRP's), and

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' Health-Physics Procedures (HPP's). The inspectors reviewed the descrip-

tion of ' the L liquid radwaste system in the FSAR (section 11.2). The

description w'as reviewed to . compare it to the actual operation system.

- The in'spectors ' also reviewed the .LWRP's, SOP's and HPP's and they appear

to be acceptable. .This item is. closed.

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4. Monthly Surveillance Observation (61726) i

The inspectors observed surveillance activities of safety related systems i

and components to ascertain that these activities were conducted in

accordance with license requirements. The inspectors. observed portions of

selected surveillance tests including all aspects of one major surveill-

ance 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 that the systems were properly returned

to service. The following specific surveillance activities were observed:

STP 120.006 Emergency:Feedwate'r Valves. Backup Air Supply Test

STP 127.001 Pressurizer Block Valve Operability Test

STP 125.002 -Diesel Generator Operability Test- l

STP'125.008 "A" Diesel Generator Refueling Operability Test (R) '

STP 125.009 "B" Diesel Generator Refueling Operability Test

STP 125.010 Integrated Safeguards Test ("A" Train)

STP 146.002 Reactor Makeup Water System Refueling Alignment-

Verification 1

STP 134.001 Shutdown Margin Calculation

STP 303.012. Steam Generator "B" Steam Pressure Instrument (PT-486)

Operational Test

STP 106.002 Rod Position Indication Operational Test

STP 310.006 NIS Power Range (N-42) Calibration

STP 130.003 Valve Operability Testing (Mode 1,2, & 3)

STP 105.001 Charging / Safety Injection Pump Test

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STP 112.003 Reactor Building Spray System Valve Operability Test  !

STP 123.001 Service Water System Valve Lineup Verification

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, 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 accomp -

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lished by qualified personnel. The : inspectors independently verified that;

equipment was properly tested before being returned to service. Addition-

ally, 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- t

system. The.following specific maintenance ~ activities were observed:

MWR'8700498 Repair packing leak on XVG067FS

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.PMST 0077250' Inspect / repair relay' room unit damper

PMST.0085229 Inspect / replace filter' system for air handling unit "A"

in switchgear room

MWR 8700616 Repair valve XV607503-AC

-MWR 8601157 Repair sheared pinion for motor operated valve

XVG03113A-0-SW

PMST-0089382 Inspect / repair component cooling heat exchanger isolation

valve XVG09625-0-CC

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PMST 0089383 ' Inspect / repair component cooling heat exchanger isolation

valve XVG09626-0-CC

MWR 8700085 Align and stake spherical bearing MKRHH0211-RH

=MWR 87 WOO 28 Install and remove test equipment in support of cycle 4

start up testing

MWR 8700645 Repair manual operator XVB03106A-SW

No violations or deviations were identified.

6. Operational Safety Verification (71707)

A. The inspectors toured the cc ctrol 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

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orders jumper /t,jpass controls, computeriprintouts and annunciators.

Tours of other plant ' areas were conducted t'o; verify , equipment oper- y

ability,.. control of ignition. sources and combustible materials,7 the

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condition of' fire detection' an.d extinguishing equipment,- the' control  ;

w of. maintenance and surveillance activities in progress, the.-imple-

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plan. : Tours )were conducted during ' normal and random off: hour

periods.

.B. At approximately 6:30 p.m. on May 26, with the plant in Mode 3 and

preparing for a plant startup for refueling, - the inspectors ~ were,

o notified that the licensee had detected a leak in the reactor coolant i

seal ' injector 'line to the reactor coolant pump. Since.TS-3.4.6.2'

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allows no . pressure boundary leakage in Modes 1,2,3 and _4, the  ;

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' licensee followed the' applicable action statement and proceeded .to

cold. shutdown. The. inspectors were additionally informed that' this ']

event had been. classified in' accordance with the Licensee's Radiation

Emergency Plan as an Unusual Event and. that the applicable- Federal, l

1 State and Local authorities were being notified. The plant subse- i

quently proceeded to cold shutdown to perform the necessary repair, l

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The' inspectors, on the morning. of May 87, , reviewed the status logs-

and records applicable to the event. The Control Room Log -indicated: ')

that the Unusual Event had been declared:at 6:20 p.m., on May 26. A .i

review of the Restoration and Removal (R & R) Log indicated that the ..

leak had been identified and a R &.R checksheet, RR #870334 had been

filled out at 4:10 p.m. , hours on May 26, or approximately 2. hours

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and 10 minutes prior to event classification. Subsequent. interviews

with ' plant -personnel indicated that leakage was detected in . the

reactor building-at approximately 10:00 a.m., on May>26. At approxi -

, mately.2:00 p.m. another entry was made into the reactor building to 4

locate the exact point of the leaki At approximately 3:00 p.m.', the j

shift supervisor was notified of the precise location of the leakage.

The event was finally classified as Reactor Coolant System Pressure

Boundary Leakage and the plant entered the Unusual Event at 6:20. p.m. ,

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10 CFR 50.54(q) requires the licensee to follow and maintain in

effect an emergency plan. The licensee Radiation Emergency Plan and

Emergency Preparedness Procedures implements this requirement, i

Section 4.1 of the V.C. Summer Nuclear Radiation Emergency P.lan

requires that the on-duty shift supervisor be notified of situations

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that' exist which may present a real or potential hazard. After this

notification, the shift supervisor will assess the situation and

provide prompt event classification. The Emergency Action Levels  !

(EAL's) contained in the above procedures, are designed to assist in

preforming this classification. j

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Contrary to the above, licensee personnel failed t'o' follow the above

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procedurer . and promptly classify Reactor Coolant System . Pressure

4 , Boundary l.eakage as an Unusual Event. This-resulted in at least a 2 )

o hour . delay on implementing; the Emergency Plan and providing the 1

required' notifications. This is a violation, " Failure to promptly- 'l

evaluate and classify and event", 87-14-01. '

C; On May 12, 1987, while performing the Integrated Safeguards Testing

on Safety Train "A",-the Service Water. Booster Pump (SWBP) failed to

start on the sequencer. An investigation by the licensee determined ',

that this failure was due to a low suction pressure condition that 1

existed when the sequencer provided a start signal . to the SWBP. 1

Further investigation revealed that the design . condition existed j

which caused the. pump to automatically trip after being started on {

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-the sequencer. These conditions existed when the SWBP was running i

and the l pump control switch on the main control board was in the

after. start position. .These conditions caused the SWBP to trip on

low suction pressure when a loss of offsite power conditions was

initiated af ter a simulated safety injection. The pump could have

been manually restarted after the low suction pressure cleared. The

conditions' were not covered in the system or emergency operating' .{

procedures.

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TS 6.8.1.(a) requires that procedures be established. implemented and 9

maintained for those systems listed in Appendix "A" of Regulatory

Guide 1.33, Revision 2,; February 1978. -

Contrary to the above, the licensee's operating procedures for the

Service Water System failed to describe the special steps required to I

insure the SWBP's would operate under accident conditions, i.e., loss l

of offsite -power, followed by a ' safety injection with the SWBP's ]

, running prior to the event. This is a violation, " Inadequate system .4

operating procedure for the Service Water System", 87-14-02, i

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The licensee has perfornnd a modification to this system to delete

the low suction pressure trip from the control circuitry. They also

plan to remove the low pressure trip switch and its function manual i

start circuit.

Two violations were identified. )

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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

Emergency Feedwater System. The inspectors confirmed that the licensee's

system lineup procedures matched plant drawings and the as-built confi-

guration. The inspectors looked for equipment conditions and items that

might degrade performance (hangers and supports were operable, house-

keeping, etc.) and inspected the interiors of electrical and instrumenta-

tion ca'oinets for debris, loose material, jumpers, evidence of rodents,

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u 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.

L No violations or deviations were identified.

8. Plant Startup from Refueling (71711)

The inspectors reviewed plant ~ activities associated.with recovery from the

refueling ' outage that began' in March,1987. The inspectors verified that

safety systems disturbed or modified during the outage were tested and

returned to an _ operable status 'pr.ior to plant startup. The inspectors

performed a system walkdown' of the Emergency Feedwater 1 System, Reactor

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Building Spray Systems, Emergency Diesel Generator Fuel Oil Sy s tem ,-

Emergency Diesel Generator, and the Emergency Power System-to verify that

the systems were properly aligned. The inspectors' reviewed the licensee's

completed system -line up check lists ' for other major safety systems

disturbed during the outage._ The inspectors also observed portions of the

checks conducted on the Rod Control and Control Rod Position Indication

System. The plant is: presently in Mode 5 preparing systems to return to.

unit to power operation.

.No violations'or deviations were identified.

.9. Onsite Followup of Events and Subsequent Written Reports (92700, 93713,

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93702)

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

Part 21_ Reports 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 condi-

tions, and licensee procedures and controls. . Based upon this review the

following items are closed:

LER 85-033 Reactor vessel level indication system error

LER 87-002 Failure to establish required firewatch. patrol

LER 87-003 Missed surveillance on diesel fire pump starting battery

LER 84-06 Overcurrent protection devices for plant paging system not  !

included in table 3.8.1 of T.S. 3.8.4 l

.LER 85-09 Inadequate containment penetration protection devices

LER 86-18 Personnel overexposure; radioactive contamination detected  !

on an individual s hand exiting the radiation control area.

This item is administrative 1y closed. It will be tracked ,

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under violation 86-22-01

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LER 84-31 Omission of circuits from plant TS

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'(Closed) .10 CFR 21 Report P2186-01, Errors in reactor vessel water level

' instrumentation system; steam density . circuit using 1 summing . amplifier

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vy,' for both . full and wide range. The licensee installed two summing

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. amplifiers 'and followed the guidance recommended by Westinghouse to

resolve this problem. The changes were implemented under MRF 32134'and

MWR's 32134.0001 and ' 32134.0002, which .were_ completed during the third

'refal.ing outage. The inspectors also verified that applicable changes to

the Emergency Operating Procedures had been implemented. This item and.

the applicable LER 85-33 are closed.

(Closed).10 CFR 21 Report P2185-02, Cracked stem assembly detected in 3/4 ,

inch.Yarway welbond valve bar stock used in stem. The inspector verified I

that the licensee had received this report. The licensee's. review of-this

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item determined that 13 valves with stems made from this heat' lot had been

supplied to the V.C. Summer station. Further review revealed' that all

valves are 'used in manual application. They are not used in radioactive

systems and any leakage as a result of a cracked stem would be a nuisance

but not a hazard. The licensee plans no further action on this item.

These components will be replaced as required under the normal maintenance

programs. This item is closed.

(Closed) 10 CFR 21 Report P2186-03, BBC Brown Boveri 600/800kV circuit

breakers' wire harness packing gear in _ contact with wiring harness which

wore a hole through the insulation and several wires in the harness. The

inspectors verified that the licensee had received and reviewed this

.information. 'As a result of the above,- the licensee conducted a

100 percent inspection of safety related applications and a sampling of

nonsafety applications. .This inspection did not identify any deficien-

'cies. As a future preventative measure, the licensee has added a step to

the maintenance procedure, ITE Air Circuit Breaker Maintenance (EMP

405.002), to inspect for this item while performing future maintenance of'

these breakers. The inspectors consider this action acceptable. This

item is closed.

No violations or deviations were identified.

10. Design, Design Changes, and Modifications (37700)

The inspectors reviewed five design changes, listed below, not previously

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

in accordance with the 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 l

conducted a review and evaluation of test results and that these test i

results were within previously established acceptance criteria and that 1

any test deviations were resolved and necessary retesting was accomplished

as appropriate, (4) that operating procedure modifications were made and

approved in accordance with TS, and (5) that as-built drawings were

changed to reflect the modifications. The inspectors observed (1) that

change activities were conducted in accordance with the appropriate

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specifications, drawings, and other requirements, (2) that acceptance and

startup testing of modifications were conducted in accordance with techni-

cally 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 l

the outstanding facility change requests. (FCR's) and determined that an j

excessive backlog was not developing.

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Steam generator U bend stress relief

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MRF 21134

MRF 21135 Steam generator tube shot peening

MRF 10723 Installation service inspection of service water pumps flow

indication i

MRF 20497 Reactor coolant pump space heaters thermal overloads

MRF 20720 Post accident monitoring system neutron flux monitor  !

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MRF 32356 Installation of new timing relays in panels XPN 5402 SW and' i

XPN 5403 SW for chillers A, B & C

No violations or deviations were identified,

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Docket No. 50-395

License No. NPF-12

South Carolina Electric and Gas Company

ATTN: Mr. D. A. Nauman

Vice President, Nuclear Operations

P. O. Box 764 (167)

Columbia, SC 29218

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Gentlemen:

SUBJECT: NOTICE OF VIOLATION

(NRC INSPECTION REPORT NO. 50-395/87-14)

This refers to the Nuclear Regu'latory Commission (NRC) inspection conducted by

R. L. Prevatte from May 5-31, 1987. The inspection included a review of activi-

ties authorized by NRC Operating License No. NPF-12 for your V. C. Summer Nuclear

Facility. At the conclusion of the inspection, the findings were discussed

with those members of your staff identified in the enclosed report.

Areas examined during the inspection are identified in the report. Within these

areas, the inspection consisted of selective examinations of procedures and

representative records, interviews with personnel, and observation of activi-

ties in progress.

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The inspection findings indicate that certain activities violated NRC require- i

ments. The violations, reference to pertinent requirements, and elements to be I'

included in your response are presented in the enclosed Notice of Violation.

I The responses directed by this letter and the enclosures are not subject to the

clearance procedures of the Office of Management and Budget issued under the

Paperwork Reduction Act of 1980, PL 96-511. i

( In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,

Title 10, Code of Federal Regulations, a copy of this letter and its enclosure '

will be placed in the NRC Public Document Room.

Should you have any questions concerning this letter, please contact us.

Sincerely, j

Luis A. Reyes, Director

Division of Reactor Projects

Enclosures: (See page 2)

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