ML19296C937

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Summary of 800129 Meeting W/Util & B&W in Bethesda,Md Re Mods Including Auto Closure of Block Valves for Power Operated Relief Valves & Addition of Anticipatory Reactor Trip Upon Loss of Main Feedwater.More Analysis Needed
ML19296C937
Person / Time
Site: Midland
Issue date: 02/14/1980
From: Hood D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8002290090
Download: ML19296C937 (5)


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FEB 1.i 120 Docket Nos.: 50-329/50-330 APPLICANT: CONSUMERS POWER COMPANY FACILITY:

MIDLAND PLANT, UNITS 1 & 2

SUBJECT:

SUMMARY

OF JANUARY 29, 1980 MEETING ON SELECTED RESPONSES C:'

B&W SYSTEM SENSITIVITY On January 29, 1980 the NRC staff met in Bethesda, Maryland with Consumers Power Company (the applicant) and Babcock & Wilcox (B&W) to discuss certain responses from a December 4,1979 letter regarding the staff's 10 CFR 50.54(f) requests of October 25, 1979 on B&W System Sensitivity. Meeting attendees are listed in Enclosure 1.

The items of discussion were limited to certain proposed modifications in the applicant's response for which staff feedback or preliminary concurrence was requested. The modifications are:

(a) Automatic closure of block valves for the power-operated relief valves (PORV) using an actuation signal for the eng1rieered safety features systems; (b) Addition of an anticipatory reactor trip upon total loss of main feedwater; (c) Restoration of setpoints for PORV and high primary pressure to those proposed prior to IE Bulletin 79-05C; and, (d) Upgrading and qualification of PORV to safety grade requirements.

The staff stated that preliminary concurrence of these modifications was not possible at this time. The staff noted that the applicants analyses are not necessarily the worst case and that the influence of the modifications upon other transients and accidents have not been provided. Moreover, the staff stressed the need to examine these and other proposed modifications in the context of improved operational safety as discussed in Section 2 of NUREG-0585, "TMI-2 Lessons Learned Task Force Final Report". This includes the need for quantitative assessments of the degree of improvement to be expected from the proposed modifications (e.g., so many fewer reactor trips or challenges to the protection systems, degree of reduction in human error potential, etc.) compared to the alternatives (e.g., IE Bulletin 79-05C setpoints, etc. ). The staff also stressed the need to examine the proposed modifications in light of the weaknesses in current deterministic design requirements which are the subject of Section 3 of NUREG-0585.

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. tLb 11ISSO The discussions by B&W of revised setpoints (item (c) above) included a handout,

" Table 1 - Effect of Revised Set-Points and Anticipatory Reactor Trip on Trip Frequency" (Enclosure 2). The table shows, for example, that the tri for B&W operating plants doubled (from 0.23 to 0.48 trips per month) p rate after the setpoints were revised by IE Bulletin 79-05C.

The staff indicated that schedule infonnation is needed for the various decisions, studies and modifications identified in the applicants response.

The staff also requires additional technical infonnation and will be issuing further requests shortly.

For example, the staff noted that the response references a generic B&W topical report, BAW-1564 on the reliability of the Integrated Control System (ICS), but fails to discuss differences between the Midland ICS due to process steam demand and the generic ICS design.

Further information is needed regarding the stability of the ICS design in view of the unique aspects of the Midland secondary system design and the influence of this stability upon challenges to the reactor protection system and regarding unique opportunities for human error in the Midland design.

Differences in analytical models used by B&W and the IRT code used by Brookhaven also need to be better understood.

The staff also indicated a need to better understand the capabilities and limitations of the B&W simulator for secondary-induced transients.

It was suggested that a visit by the staff may be helpful in this regard.

oo Light Water Reactors Branch #4 Division of Project Management Enclosures :

As stated cc: See next page

Consumers Power Company FEb i 1330 ccs:

Michael 1. Miller, Esq.

Mr. S. H. Howell Isham, Lincoln & Beale Vice President Suite 4200 Consumers Power Company One First National Plaza 212 West Michigan Avenue Chicago, Illinois 60603 Jackson, Michigan 49201 Judd L. Bacon, Esq.

Managing Attorney Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Mr. Paul A. Perry Secretary Consumers Power Company 212 W. Michigan Avenue

.lackson, Michigan 49201 Myron M. Cherry, Esq.

One IBM Plaza Chicago, Illinois 60611 Mary Sinclair 5711 Summerset Drive Midland, Michigan 48640 Frank J. Kelley, Esq.

Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 Mr. Wendell Marshall Route 10 Midland, Michigan 48640 Grant J. Merritt, Esq.

Thompson, Nielsen, Klaverkamp & James 4444 IDS Center 80 South Eighth Street Minneapolis, Minnesota 55402 Mr. Don van Farowe, Chief Division of Radiological Health Departnent of Public Health P. O. Box 33035 Lansing, Michigan 48909 Resident Inspector / Midland NPS c/o U.S. Nuclear Regulatory Commission P. 0. Box 1927 Midland, Michigan 48640

ENCLOSURE 1 JANUARY 29, 1980 ATTENDEES Name Organization J. J. Zabritski CPC0 - Proj. Lic. Eng.

D. T. Perry CPC0 - Proj. Mech.

M. J. Salerno CPC0 R. J. Finnin B&W - Licensing R. L. Reed B&W - Proj. Mgmt.

S. Israel NRC T. Novak NRC B. L. Siegel NRC:RSB N. Wagner NRC:RSB J. P. Joyce NRC:ICSB J. Guttmann NRC:AB A. Bournia NRC:DPM D. S. Hood DPM:NRR

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