ML20133L796

Insp Rept 50-458/85-62 on 850816-0915.Violation Noted: Administrative Procedure ADM-003 Requirements Not Fully Implemented for Surveillance Test Procedures for Semiannual Calibr of Source Range Monitor Channels A,B,C & D

ML20133L796
Person / Time
Site:	River Bend
Issue date:	10/09/1985
From:	Chamberlain D, Craig Harbuck, Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20133L760	List: IR 05000816/2009015 ML20133L757 ML20133L796
References
50-458-85-62, NUDOCS 8510240312
Download: ML20133L796 (7)

See also: IR 05000458/1985062

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APPENDIX B

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/35-62 License: NPF-40

Docket: 50-458

Licensee: Culf States Utilities Company (GSU)

P. O. Box 2951

Beaumont, Texas 77704

Facility Name: River Bend Station (RBS)

Inspection At: River Bend Station, St. Francisville, Louisiana

Inspection Conducted: August 16 through September 15, 1985

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Inspectors:  ; , h-23-38

D. D.VChamberlain, Senior Resident Inspector Date

(pars. 1,2,3,5,6,7, nd 8)

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.f.(larb)(ck,ReactorMnspector, Project Da te'

V Section 4, Reacto Projects Branch (par. 4)

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I .f.P Jaufon, Chief,ProjectSectionA Date

{ Rea[cto( Projects Branch (par. 7)

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W. M. McNeill, ~Reactbr Inspector, Operations Ddte'

Section, Reactor Safety Branch (par. 7)

I Approved: /[M hI

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.[.P./Jaudc[n,~ Chief,ProjectSectionA. Date

l 6 Reactor Projects Branch

8510240312 85 j50

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. Inspection Summary-

Inspection Conducted August 16 through September 15, 1985 (Report 50-458/85-62)

Areas Inspected: Routine, unannounced inspection of site tours, initial

fuel loading witness, overall startup test program review, surveillance

testing baseline witness, operational safety verification, and licensee

quality concern program review. The inspection involved 235 inspector-

hours onsite by four NRC inspectors.

Results: Within the areas inspected, one violation was issued in the

area of initial fuel loading witness (failure to follow an administrative

Procedure, paragraph 3).

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DETAILS

1. Persons Contacted

Principal-Licensee Employees

• B. E. Boyer, Environmental Analyst

W. H. Cahill, Jr. Senior Vice President, River Bend Nuclear

• J. V. Conner, Supervisor, Environmental Services

• T. C. Crouse, Manager, Quality Assurance (QA)

• J. C. Deddens, Vice President River Bend Nuclear Group

D. R. Derbonne, Supervisor, Startup and Test

S. Finnegan, Control Operating Foreman

• P. E. Freehill, Superintendent, Startup and Test

• D. R. Gipson, Assistant Plant Manager, Operations

P. D. Graham, Assistant Plant Manager, Services

• M. A. Harrington, Senior Environmental Analyst

D. Hartz, Shift Supervisor, Operations

R. W. Helmick, Director, Projects

• B. D. Hey, Licensing Engineer

K. C. Hodges, Supervisor, Quality Systems

R. Jackson, Shift Supervisor, Operations

D. Jernigan, Engineer, Startup and Test

G. R. Kimmell, Supervisor, Operations QA

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A. D. Kowalczuk, Assistant Plant Manager, Maintenance

T. Lacy, Shift Supervisor, Operations

• J. M. McGhee, Radwaste Foreman

• E. R. Oswood, Engineer, QA

• T. L. Plunkett, Plant Manager

• S. R. Radebaugh, Assistant Superintendent, Startup and Test

• C. A. Rohrmann, Technical Training Coordinator

• J. E. Spivey, Engineer, QA

R. B. Stafford, Director, Qua'ity Services

• L. R. Thompson, Supervisor, Instrumentation and Control

P. F. Tomlinson, Director, Operation QA

C. Warren, Shift Supervisor, Operations

• R. G. West, Supervisor, Startup and Test

' Stone and Webster

.F. W. Finger, III, Project Manager, PTO

B. R. Hall, Assistant Superintendent, Field Quality Control

R. L. Spence, Superintendent, Field Quality Control

The NRC senior resident inspector (SRI) also interviewed additional

licensee, Stone and W'ebster (S&W), and other contractor personnel during

the inspection period.

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• Denotes those persons that attended the exit interview conducted on

September 20, 1985. NRC inspectors, R. E. Baer and J. B. Nicholas, also

attended the exit interview.

2. Site Tours

The SRI toured areas of the site during the inspection period to gain

knowledge of the plar.t and to observe general job practices. Special

attention was given to the containment / refueling areas in preparation for

initial fuel load which began on August 31, 1985.

No violations or deviations were identified in this area of inspection.

3. Initial Fuel Loading Witness

This area of inspection was conducted to ascertain the conformance of the

licensee to license and procedural requirements, to observe operating

staff performance, and to ascertain the adequacy of fuel loading records

during initial fuel loading at River Bend. Gulf States Utilities (GSU)

received the operating license on August 29, 1985, and the first fuel

bundle was placed in the reactor core at approximately 3:30 a.m. on August

31, 1985. The SRI witnessed the placing of the first fuel bundle and

observed fuel loading activities throughout the inspection period. During

the review of the source range monitor nuclear instrument calibration

records, it was noted by the SRI that administrative procedural

requirements were not fully implemented for surveillance test procedures

STP-503-4203 (completed 8/02/85), STP-503-4204 (completed 8/03/85),

STP-503-4205 (completed 8/06/85), and STP-503-4206 (completed 8/02/85) for

the semiannual calibration of source range monitor channels A, B, C, and

D. The STPs were not followed exactly, Temporary Change Notices (TCN)

85-1405 and 85-1406 were issued and approved without the reason for the

change being specified on the TCN form, and other approved TCNs were not

fully implemented for the continuation of the work activity.

Examples of the failure to follow the STP procedures exactly and the

failure to fully implement TCNs include:

. The following procedure steps were marked NA and not completed and

there was no documented evidence that the steps did not apply to the

test conditions at that time:

STP-503-4203 STP-503-4204 STP-503-4205 STP-503-4206

7.1.109.2 7.1.116.18 7.1.127.13 7.1.116.18

7.1.127.13 7.1.116.19 7.1.127.14 7.1.116.19

7.1.127.14 7.1.127.13 7.1.127.15 7.1.118.5

7.1.127.15 7.1.127.14 7.2.42 7.1.122.1

7.2.6.5 7.1.127.15 7.1.127.13

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STP-503-4203 STP-503-4204 STP-503-4205 STP-503-4206

7.2.6.6 7.2.6.3 7.1.127.14

7.2.6.7 7.2.6.5 7.1.127.15

7.2.6.8 7.2.6.6 7.2.1

7.2.6.12 7.2.6.7 7.2.6.3

7.2.43.3 7.2.6.8 7.2.6.5

7.2.43.5 7.2.6.12 7.2.6.6

7.2.43.3 7.2.6.7

7.2.43.5 7.2.6.8

7.2.6.12

. Table IX of STP-503-4205 for C51-K600C, SRM Period Meter Remote,

listed a minimum value for steps 7.1.72.11 and 13 of "not on peg" but

-both the as-found and the as-left values were "on downscale peg."

Maintenance Work Request MWR 005048 listed in test results was for

replacement of meter C51-K601C and no MWR could be located for meter

C51-K600C.

. TCN 85-1436 changed and rearranged steps 7.2.40, 7.2.41, and 7.2.42

of STP-503-4203, but the original procedure steps were signed as

r complete.

. TCN 85-1214 added restoration step 9 to STP-503-4205, but restoration

step 9 was not signed as complete.

. TCN 85-1440 changed step 7.1.109 of STP-503-4206, but both the

original step 7.1.109 and the TCH step 7.1.109 were signed as

complete. .

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. TCN 85-1453 changed steps 7.1.119.5, 7.2.19, and 7.2.32 of

STP-503-4206, but none of these steps were signed as complete.

. TCN 85-1454 changed and rearranged steps 7.2.40, 7.2.41, and 7.2.42

of STP-503-4206, but the original procedure steps were signed as

complete.

This failure to follow administrative procedure requirements is an

apparent violation (458/8562-01) of NRC requirements.

During the initial fuel load conduct, activities in the control room .

appeared disorganized, but GSU management took immediate action to limit

administrative activity at the control operator tables and shift briefings ,

were conducted by the shift supervisor at the beginning of each shift to

help alleviate confusion regarding planned shift activities. Also, daily

planning meetings were conducted to coordinate activities and to discuss

problems encountered. Daily improvement was noted in the conduct of

control room activities.

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During this inspection period, four unplanned reactor protection system

(RPS) actuations occurred, and all four were called in to the

headquarter's duty officer as required. The licensee plans to issue

Licensee Event Reports (LERs) for these RPS actuations. None of the

unplanned RPS actuations caused any problems with fuel loading activities

and the SRI will follow up during normal LER review during a future

inspection. There were also two cases of potential loose parts in the

reactor vessel which will require additional follow up by the SRI. One

case was a lost snao cing from a pin on the fuel grapple and another case

was a "D-Ring" and two electrical pin connectors from the electrical cable

going to the fuel grapple engaged limit switch. Both of these conditions

were repaired with direction from General Electric (GE) and the licensee

received notification from GE that fuel loading could continue. GE still

has to complete a lost parts analysis on the missing parts. This item

will remain open (458/8562-02) pending the results of the GE lost parts

analyses. Although problems have been encountered during fuel loading,

the SRI concluded that the licensee had been identifying these problems

and taking'the required actions promptly. The SRI also concluded that the

licensee's approach to initial fuel loading activities was cautious.

4. Overall Startup Test Program Review

The purpose of this area of the inspection was to ascertain whether the

licensee has developed administrative controls which will assure that the

startup test program will be prepared, performed, and evaluated in

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accordance with regulatory requirem!nts.

The NRC inspector verified that the licensee's startup test program, as

described in the FSAR, appears to fulfill their commitment to follow the

test program outlined in Regulatory Guide 1.68, " Initial Test Programs for

Water-Cooled Nuclear Power Plants," Revision 2, August 1978. It was also

determined that the licensee had identified and sequenced the tests to be

. performed, and had nearly completed issuing the individual test

procedures.

The NRC inspector verified that adequate formal administrative measures

had been established to govern the conduct of testing and the evaluation

of test results.

There was some initial concern with the method of scheduling startup test

activities, but this concern was alleviated at this time with the conduct

of daily planning meetings and with the preshift briefings by the shift

supervisors.

The NRC inspector reviewed the licensee's startup test organization end

found that the operating organization (operations) had been assigned

overall responsibility for startup test activities and that the interfaces

between startup test engineers and the on-shift operating staff had been

well defined.

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The NRC inspector also reviewed the licensee's program for maintaining

test and measurement equipment to be used during startup testing. No

problems were noted.

No violations or deviations were identified in this area of the

inspection.

5. Surveillance Testing Baseline Witness

The SRI witnessed two unsatisfactory attempts to perform STP-309-0601,

" Division I LOP /LOCA Test." This test fulfills certain 18-month

surveillance test requirements for the division I diesel generator. One

test was unsatisfactory due to a procedure problem and the other due to an

unexplained failure of the division I diesel to start. The procedure

problem was corrected and the division I diesel was successfully started

on subsequent occasions. However, the SRI will review the licensee

actions to identify the cause of the one failure of the diesel to start

(0 pen Item 8562-03).

No violations or deviations were identified in this area of inspection.

~6. Operational Safety Verification

This area of inspection was conducted to assure that the facility is being

operated safely and in conformance with regulatory requirements during

initial operational mode 5 activities. Refueling is described as

operational condition mode 5 by River Bend Technical Specifications. The

SRI basically conducted a review of required mode 5 system alignments as

observed from control room indications and monitored control room

activities throughout the inspection period.

No violations or deviations were identified in this area of inspection.

7. Licensee Quality Concern Program Review

The licensee's quality concern program was described _in NRC Inspection

Report 50-458/85-25. The SRI, assisted by Region IV personnel, continued

to review licensee actions on individual cases.

No violations or deviations were identified in this area of inspection.

8. Exit Interview

An exit interview was conducted on September 20, 1985, with licensee

representatives (identified in paragraph 1). During this interview, the

SRI reviewed the scope and findings of the inspection.

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