ML20210C329

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/86-20.Addl Info Re Review of P&ID Requested,Per 860911 Telcon.Supplemental Info Requested within 30 Days of Ltr Date

ML20210C329
Person / Time
Site:	River Bend
Issue date:	09/16/1986
From:	Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	William Cahill GULF STATES UTILITIES CO.
References
NUDOCS 8609180311
Download: ML20210C329 (2)

See also: IR 05000458/1986020

Text

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Gulf States Utilities

ATTN: William J. Cahill, Jr. -

Senior Vice President-

River Bend Nuclear Group

P. O. Box 220

St. Francisville, Louisiana 70775

Gentlemen:

Thank you for your letter of August 29, 1986 , in response to our letter

and the attached Notice of Violation dated July 30, 1986' As a result .

of our review, we find that additional information, as discussed with your

Mr. E. Grant during a telephone call on September 11, 1986, is needed.

Specifically, we need more information on the review of piping and instrument

drawings that we understand you are conducting.

Please provide the supplemental information within 30 days of the

date of this letter..

Sincerely,

Original signed By

J. E. Gagliardo

J. E. Gagliardo, Chief

Reactor Projects Branch

cc:

. Gulf States Utilities

ATTN: ~J. E. Booker, Manager-

Engineering, Nuclear

Fuels & Licensing

P. O. Box 2951

Beaumont, Texas 77704

Louisiana State University,

Government Documents Department {

Louisiana Radiation Control Program Director

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GULF STATES UTELETIES COMPANY . j

river SEND STATION POST OFFICE 80x 220 ST FR ANCISvtLLE. LOUISIANA 70775

AREA CODE 504 635 6094 346 8651

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August 29, 1986

RBG- 24275

File Nos. G9.5, G15.4.1

Mr. Robert D. Martin, Regional Administrator

U.S. Nuclear Regulatory Commission

Region IV . ,_. , , 3

611 Ryan Plaza Drive, Suite 1000 , yI5 O, .s t ." U .

Arlington, TX 76011 4

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Dear Mr. Martin: SEP - 41986 "; j -

River Bend Station - Unit 1 - 'dO

Refer to: Region IV '

Docket No. 50-458/ Report 86-20Y

This letter is in response to the Notice of Violation

contained in NRC Inspection Report No. 50-458/86-20. The

inspection was performed by Messrs. D. D. Chamberlain and W. B.

Jones during the period May 1 through June 15, 1986, of

activities authorized by NRC Operating License NPF-47 for River

Bend Station Unit No. 1.

Gulf States Utilities Company's (GSU) response to the Notice

of Violation 8620-01 and 8620-02 is provided in the enclosed

attachment. This completes GSU's response to the Notice of

Violation.

Sincerely,

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W. J. Cahill, Jr.

Senior Vice President

River Bend Nuclear Group

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• UNITED STATES OF AMERICA

EUCLEAR REGUIATORT CGAESSION

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STATE OF UMTISIAEA 5

FARISn OF WEST FILICIANA 5 .

In the Matter of I Docket Bos. 50-458

OULF STATES UTILITIES CGIFANY l

(River Bend Station,

Unit 1) .

AFFIDAVIT

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W. J. Cahill, Jr., being duly sworn, states that he is a Senior

Vice President of Gulf States Utilities Company that he is authorized

on the part of said Company to sign and file with the Nuclear Rggulatory

Coussis sion the documents attached hereto and that all such documents

are true and correct to the best of his knowledge, information and belief.

W. Cahill, Jr. //

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Subscribed and sworn to before me, a Notary Public in and for the

State and Parish above named, this /7 day of duud ,198

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anW.Middlebloops

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otary Public in and for

West Feliciana Parish,

Louisiana

My Commission is for Life.

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ATTACHMENT

Response to Notice of Violation 50-458/8620-01

Level IV

FAILURE TO FOLLOW ADMINISTRATIVE PROCEDURES FOR ISSUANCE OF

TEMPORARY CHANGE NOTICES (TCN's)

REFERENCE:

Notice of Violation -

Letter to W. J. Cahill, Jr. from J. E.

Gagliardo dated July 30, 1986.

REASON FOR ,THE VIOLATION

During an NRC inspection conducted on May 1 through June 15,

1986, the inspectors identified a failure to follow

Administrative procedures. As a result of personnel oversight,

I&C Maintenance Technicians failed to comply with the procedural

requirements of Administrative Procedure .

(ADM)-0003,

" Development, Control and Use of Procedures" when initiating

Temporary Change Notice No. 86-0581 for procedure STP-051-4210.

This resulted in .an official work copy of- the procedure

containing duplicate page numbers with different Temporary Change

Notice (TCN) Numbers on each page.

CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED

On April 10, 1986,.orior to the NRC inspection, Memorandum No.

PAS-86-141 was issued identifying procedures with two or 'more

TCN's having duplicate pages with different changes. The

memorandum identified the deficiencies with STP-051-4210 and

requested that the faulty TCN's be corrected.

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In response to Memorandum No. PAS-86-141, Procedure STP-051-4210,

Revision 2, was submitted for revision on April 20, 1986 to

incorporate the outstanding TCN's and eliminate the duplicate

pages. Revision 3 of STP-051-4210 was approved and issued on

July 30, 1986.

CORRECTIVE STEPS WILL BE TAKEN TO AVOID FURTHER VIOLATIONS

The I&C Procedure Coordinator reviewed the TCN deficiencies with

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the responsible individuals and instructed the individuals to

l comply with the requirements of ADM-0003 when initiating future

l TCN's.

Memorandum No. PIC-M-86-116 was issued on July 9, 1986 requesting

that TCN's issued by the I&C Maintenance Department be routed

through the I&C Procedure Coordinator prior to obtaining the

Shift Supervisor's signature. The I&C Procedure Coordinator is

responsible for reviewing TCN's being issued to assure compliance

with ADM-0003 and evaluates the necessity of the TCN. The

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ATTACHMENT (Cont'd)

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routing of the TCN through the I&C Procedure Coordinator will be

discontinued when the number of TCN's being issued is-

significantly reduced.

To prevent recurrence of similar violations, ADM-0003 was revised

on 8/6/86 to clarify procedural instructions for issuing a TCN to

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a page that has been previously changed by a TCN.

DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED

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STP-051-4210 was revised on July 30, 1986 to incorporate the

outstanding TCN's and eliminate the duplicate pages.

River Bend Station is currently in compliance.

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ATTACHMENT (Cont'd)

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Response to Notice of Violation 50-458/8620-02

Level IV

FAILURE TO CONTROL ACTIVITIES AFFECTING QUALITY-

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REASON FOR THE VIOLATION

A walkdown of the "C" Residual Heat Removal (RHR) system by NRC

inspectors identified the following differences between actual

system configurations and controlling instructions, procedures,

and drawings: 1) five pipe caps, shown~ as installed on

Engineering, Piping _and Instrument Drawing PID-27-C were not

installed, 2) valve E12*MOVF064C, which was shown closed on

Engineering, Piping and Instrument Drawing PID-27-7C was open, 3)

valve E12*VF063C was not locked, although Engineering, Piping and

Instrument Drawing PID-4-3C showed this valve to be locked, 4)

differences were found between Engineering, Piping and Instrument

l Drawing PID-27-7C and System Operating Procedure, SOP-0031, as to

which valves were locked in position.

Item 1

Investigations to determine the reason that the pipe caps are

missing, although shown installed on Engineering, Piping and

Instrument Drawing, PID-27-7C, are indeterminate.

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Item 2

The minimum flow valve E12*VF064C was placed in the open

position, per the SOP-0031, however, PID-27-7C showed this valve

l to be closed.

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Item 3

Operations personnel had previously performed an audit of locked

valves on the RHR system and determined valve E12*VF063C was

verified to be closed, but no lock was installed on the valve

because it was approximately twenty feet above the floor and

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considered inaccessible.

! Item 4

j Operations was aware of the differences between the two existing

system drawing types and the SOP's and was in the process of

correcting this situation by revisions to the PID's and the

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SOP's. .The cause of these discrepancies was determined to be the

lack of configuration management programs to ensure procedure

updates on the issuance of changes to drawings and drawing

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updates to reflect commitments to lock specific valves.

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CORRECTIVE STEP WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED

The five missing pipe caps that are shown on PID-27-C have been

replaced.

Since valve E12*MOVF064C was in the proper position in accordance

with SOP-0031 it will be left in this position (i.e., open to

allow minimum flow).

Valve E12*VF063C has been locked as shown on PID-4-3C.

Operations has revised the RHR SOP to agree with existing PID's.

CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS

Nuclear Equipment Operators on rounds will take notice of missing

pipe caps and replace them. A supply of caps has been placed in

the Contrcl Room for this purpose. Additionally, Local Leak Rate

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Testing (LLRT) Procedures will include a step to ensure

, replacement of caps which are removed for LLRT. Nuclear Plant

Engineering (NuPE), along with Stone & Webster (S&W) is in the

process of determining which valve caps are required for a system

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to meet its intended design.

PID's will be revised to indicate valve position for a normal

mode of operation, and Station Operation Manual (SOM) procedures

will govern actual valve position.

A new procedure, Operation Section Procedure OSP-0014, which

directly addresses the control of locked valves has been issued

by the River 3end Operations Department.

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A review of all PID's versus SOPS has been conducted. Changes to

j the procedures have been issued to agree with the PID's. A

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review of the PID's is being performed by NuPE to determine which

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valves should be locked and which should be left unlocked. NuPE

will also develop a' procedure which will delineate the locked

valve regulation requirements. Included in this review will be

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the necessary changes of PID?s to match these requirements. Upon

l completion, it is expected this will decrease the number of

l valves required to be locked.

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Adequate configuration management control procedures are

currently in place. All changes to locked valve status will be

followed by updates to the SOP's via these controls.

DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED

The additional procedural controls ensuring replacement of pipe

caps in Local Leak Rate Testing Procedures will be completed by

October 30, 1986.

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ATTACHMENT (Cont'd)

Valve E12*VF063C has been verified to be locked at the time of

this response.

Procedures being developed by NuPE for determining locked valve

regulation requirements will be completed by November 30, 1986.

The PID changes brought about by NuPE's reviews will be completed

by December ~31, 1986.

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