ML20128B644

Responds to 850322 Request for Addl Info Re Util 831025 Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Info Re Vendor Interface & safety-related Classification Provided

ML20128B644
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	05/17/1985
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
GL-83-28, LAC-10863, NUDOCS 8505280002
Download: ML20128B644 (3)

Text

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D DA/RYLAND h [k COOPERAT/VE

• PO. BOX 817 2615 EAST AV SOUTH . LA CROSSE WISCONSIN 54601 (608) 788 4 000 May 17, 1985 4 l

In reply, pelase refer to LAC-10863 DOCKET NO. 50-409 U. S. Nuclear Regulatory Commission Attn Mr. John A. Zwolinski, Chief Operating Reactors Branch #5 Office of Nuclear Reactor Regulation Division of Operating Reactors Washington, DC 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE (DPC)

LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS (GENERIC LETTER 83-28)

References:

(1) NRC Letter, Zwolinski to Linder, dated March 22, 1985 (2) DPC Letter, Linder to Eisenhut, LAC-9392, dated October 25, 1983 (3) NRC Letter, Generic Letter 83-28, Eisenhut to all Licensees, dated July 8, 1983 (4) DPC Letter, Linder to Crutchfield, LAC-9687, dated March 20, 1984

Dear Mr. Zwolinski:

Reference 1 requested supplemtary information regrding DPC's response (Reference 2) to Generic Letter 83-28 (Reference 3). This letter will provide additional information on the items requested.

Vendor Interface Items 2.1.2 and 2.2.2 covered vendor interface, the former of reactor trip systems, the latter for other safety-related equipment. These two topics will be discussed jointly.

As discussed in Reference 2, LACBWR is an early vintage atypical plant.

Several one-of-a-kind systems and equipment application exist. Many of equipment vendors have lef t the nuclear business, stopped manufacturing the type of equipment they provided LACBWR, or gone out of business totally. In some cases where the vendor is still in the nuclear business, they are no longer interested in equipment obsolete 20 year ago.

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. - Mr. J;hn A. Zwolin:ki, Chiaf M y 17, 1985 Operating Reactor Branch #5 LAC-10863 Therefore, LACBWR is most f amiliar with the equipment performance in a nuclear plant. The maintenance program has had to develop self-sufficiency.

Preventive Maintenance (PM) programs originally developed based on manufacturer's recommendation have been modified based on equipment performance. For example, the PM program for the Reactor Building Main Steam Isolation Valve (MSIV) was recently evaluated and adjusted with the frequency of part of the PM being decreased, but with an additional item being added to the program. The MSIV was supplied by Allis-Chalmers who is no longer in the valve business. Items have been added and removed from the PM program based on equipment service and failures.

Improved maintenance methods for some equipment have been developed over the years. This is true for mechanical, electrical and instrument maintenance.

In some cases, replacment parts have been modified based on service history.

LACBWR, however, is not an island. Experienced personnel review the INPO SEE-IN Program information, the Significant Operating Experience Reports, Significant Event Reports, and Operations and Maintenance Reminders, for applicable operating experience. While the majority of the information is not applicable, due to LACBWR's uniqueness, potentially useful information is disseminated to appropriate personnel. For some situations, additional information is requested and obtained. NRC Bulletins and Information Notices are also promptly routed to appropriate personnel.

LACBWR maintains communications with other utilites through Network, thus exchanging questions and answers with the personnel having the most detailed knowledge of equipment performance in nuclear applications. Information is exchanged on matters such as valve operating history, packing, and instrumentation. In addition, plants provide some operating experience information, which is also reviewed for applicability at LACBWR.

DPC does not want to project the impression that vendor information is ignored. Equipment operating and maintenance (0&M) manuals are controlled in accordance with Engineering Control Procedure 2, " Control of Design Documents". Following review of O&M manuals by a cognizant engineer, the O&M manuals enter the LACBWR controlled document system. Each copy of a manual is assigned a number. One copy is maintained in the QC files and is available only by sign out in accordance with the procedure.

When available, vendors are contacted when major problems arise with equipment. For example, Allis-Chalmers has been contacted on breakers and Powell has provided assistance on the Alternate Core Spray Valves. Vendors have also been contacted on replacement part selection. Sometimes vendors have been exceedingly helpful, at other times limited or adverse assistance has been provided.

As discussed above, a formal vender interface program as you describe does not exist, but interface with existing vendors does occur on an as-needed basis.

Vendor Operating and Maintenance manuals are controlled by a procedure.

Information is exchanged with other utilities. Reports provided by INPO and the NRC are reviewed and applicable information disseminated. This operating experience review program is also controlled by a procedure, which ensures LACBWR remains cognizant of significant occurrences throughout the industry.

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, , Mr. J:hn A. Zwolin-ki, Chisf May 17, 1985 Operating Reactor Branch 15 LAC-10683 Safety-Related Classification (Item 2.2.1)

Reference 2 described the LACBWR system used to identify safety-related components. A separate' listing delineating each safety-related component does not exist. The criteria for determination of whether a component or system is safety-related are available to all plant personnel. Any modification to the criteria requires a procedure change, which must be reviewed by the Quality Assurance Supervisor and the Operations Review Committee and approved by the Plant Superintendent. Since the criteria are proceduralized, unauthorized

- changes cannot be made. >

As discussed in Reference 2, the same requirements exist for review of maintenance, testing'and operating procedures, facility changes and document control for non-safety related. plant equipment (with the exception of the security system) as for safety-related equipment. Therefore, the need for the majority of plant personnel to know whether a specific component is safety-related is minimized. The availability of the safety-related criteria, however, facilitates their consultation if a questions arises.

On-line Testing (Item 4.5.3.)

'The Technical Specification change determined beneficial in the evaluation of

'on-line reactor protective system testing was submitted in Reference 4 last year.

Based on telecoms between R. Dudley and D. Lasher (NRC) and L. Goodman (DPC) on May 2, 1985 and R. Dudley and L. Goodman on May 3, 1985 no further <

information is needed on this topic at this time.

If there are any questions, please contact us.

Sincerely, DAIRYLAND POWER COOPERATIVE

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,j Frank Linder, Ge eral Manager FL:LSG:sks cc: James G. Keppler, Region III NRC Resident Inspector Richard Dudley, LACBWR Project Manager f

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