ML20136G505

Insp Rept 50-458/85-71 on 851007-11.Violation Noted: Procedures STP-051-4228 & STP-051-4201 Permitted Trip Setpoint to Be Calibr Outside Tech Spec Limits

ML20136G505
Person / Time
Site:	River Bend
Issue date:	11/01/1985
From:	Craig Harbuck, Jaudon J, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20136G493	List: ML20136G489 ML20136G501 ML20136G505
References
50-458-85-71, NUDOCS 8511220374
Download: ML20136G505 (4)

See also: IR 05000458/1985071

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APPENDIX B

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U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/85-71

Docket: 50-458 License: NPF-40

Licensee: Gulf States Utilities

P. O. Box 2951

Beaumont, Texas 77704

Facility Name: River Bend Station

Inspection At: St. Francisville, Louisiana

Inspection Conducted: October 7-11, 1985

Inspectors: /0/Jo/F.5"

M. E. Skow, Project Engineer, Project Da'te '

Section A, Reactor Projects Branch

(pars. 2, 3, 4, 5)

f .. JAAA C Nl ~ -

J .jarfuck, Project 7ngineer, Project Date

w Section A, Reactor Projects Branch

(pars. 3)

Approved: , A M /[ f

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.(Jaupon, Chief,'ProjectSectionA, Date

Rea& tor Projects Branch

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Inspection Summary

Inspection Conducted October 7-11, 1985 (Report 50-458/85-71)

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. Areas Inspected: Routine, unannounced inspect 1on of various open items and

license conditions for follow-up for possible closure.

The inspection involved 58 inspector-hours onsite by two NRC inspectors.

Results: Within the areas inspected, one violation was identified (and is

-discussed in paragraph 3).

8511220374 851105

PDR ADOCK 05000458

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DETAILS

1. Persons Contacted

Gulf States Utilities

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

• D. R. Gipson, Assistant Plant Manager

• A. D. Kowalczuk, Assistant Plant Manager

• T. C. Crouse, QA Manager

• P. E. Freehill, Superintendent

• E. R. Grant, Licensing

• E. R. Oswood, QA Engineer

• G. V. King, Plant Services Supervisor

H. M. McClellan, Compliance Group

B. E. Hey, Licensing

S. R. Radebaugh, Superirtendent

A. O. Fredien, Operations

J. E. Spivey, Operations QA Engineer

P. D. Graham, Assistant Plant Manager

R. Kosmala, Technical Staff Engineer

Others

D. Hill, Stone & Webster, Staff Specialist

H. E. Stubbs, Stone & Webster, Supervisor Field QC

0. V. B. Rice, GE, Technical Staff Engineer

• Denotes those present at exit interview

2. Technical Specifications and Implementing Procedures

The objective of this follow-up inspection to the NRC inspection

conducted April 19 through May 3, 1985 (NRC Inspection Report

50-458/85-35), was to determine whether the Technical Specifications (TS)

will be properly implemented through the approved facility procedures.

The NRC inspectors reviewed the specific inspection findings documented

l on the data sheets attached to NRC Inspection Report 50-458/85-35 that

were left open and renumbered in NRC Inspection Report 50-458/85-58 as

open items 8558-01 through 8558-24. The NRC inspectors reviewed the

procedures for adequacy and to ensure the specific issues identified in

the Data Sheets had been resolved. As a result of this review, the NRC

inspectors considered the following items CLOSED:

8558-01, 8558-03, 8558-07, and 8558-09 through 8558-24.

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3. Previously Identified Open Items

(Closed) Open Items 8558-25 and 8558-27: Changes have been made to

! STP-051-4201, Revision 3, to reflect changes in the TS. However, both

STP-051-4201 and STP-051-4228, Revision 0 have set points with a

tolerance specified arcund the set points. The TS list the set points

as a limit, using the notation 2 (greater than cr equal to) in some cases

or s (less than or equal to) in other cases.

Although there had apparently been no calibrations conducted outside of

' Technical Specifications, this situation allows the aossibility that,

should the trip point be found to exceed the " allowable value" of the TS

and thus require resetting, the reset trip point could be set within the

tolerance band of the procedure but not within the " trip setpoint" liniit

of the TS. This is is an apparent violation (8571-01). Open

Items 8558-25 and 8558-27 are closed.

(Closed) Open Item (8563-02): Review of Revision 1 to startup procedure

ST-14 " Reactor Core Isolation Cooling." This item was open because of

the many changes being made to this procedure by the licensee. The f4RC

inspector reviewed a draft copy of Revision 1 and determined that it

appeared to meet all FSAR test cornitments and wculd provide for adequate

testing of the RCIC system. This item is Closed.

(Closed) Open Item (8554-01): Control Room E&DCR files and drawings

used for training of control room operators.

This item was open to track a licensee commitment to conduct uscage

familiarization training for licensed control room operators on the E8DCR

files and system drawings in the control room. The fiRC inspector

verified that of the persons designated to be trained to meet this

cornitment, all 9 shift supervisors, all 9 shif t foremen, and 18 out of

21 fluclear Control Operators (fiC0s) had received this training. The 3

remaining NCOs had not received this training because administrative

reasons. It appeared that they would be trained prior to initial

criticality. The NRC inspectors concluded that GSU appeared to have met

their commitment. This itcm is Closed.

4. IE Bulletins

IE Bulletin fio. 83-03, " Check Valve Failures in Rcw 1:cter Cooling Systems

of Diesel Generators." This bulletin required licensees to ensure certain

check valves were tested not only in the fon<ard ficw conditions, but

also in a means to ensure internal integrity of the valve. STP-256-3301

and STP-256-3302, Division I and II Standby Service Water Valve Operability

Tests, test the check valves in the standby service water lires to the

diesel generators. The valves are tested with both forward flow and back

flow means. These are also routinely checked surveillance tests. This

item is Closed.

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5.- Licensee Identified Construction Deficiency Review

This area of inspection was conducted to review action taken on the

following licensee identified construction deficiency.

(Closed) Deficiency P. port'DR-313: "E :essive Temperature in Excitation

Cabinets" .

e Initial NRC notification date: June 7, 1985

e Final report: GSU letter RBG-21453 of July 3,1985

.The corrective action for this reportable deficiency was to provide a

source of ventilation to the subject panels, procure necessary material,

and implement the required modification. .A review of documentation by

the NRC inspector revealed that all activities related to this

modification had been completed. This item is Closed.

6. Exit Interview

An exit interview was held on October 11, 1985, with the Mr. Deddens and

other. personnel as denoted in paragraph 1 of this report. The NRC senior

resident inspector also attended this meeting. At the meeting, the scope

of the inspection and findings were summarized.

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