ML19270G805

Summary of 790511 Meeting W/Util in Bethesda,Md Re Auxiliary Feedwater Sys.List of Attendees & Matl Discussed Encl

ML19270G805
Person / Time
Site:	Point Beach
Issue date:	05/15/1979
From:	Trammell C Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-2.E.1.1, TASK-2.E.1.2, TASK-TM TAC-11692, TAC-11693, NUDOCS 7906200330
Download: ML19270G805 (4)

Text

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UNITED STATES

>,,, 3 j NUCLEAR REGULATORY COMMISSION j

t WASHINGTON, D. C. 20555

%.((. f May 15, 1979 Docket Nos. 50-266 and 50-301 LICENSEE: Wisconsin Electric Power Company FACILITY: Point Beach Nuclear Plant, Unit Nos.1 and 2

SUMMARY

OF MEETING HELD ON MAY ll,1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEM AT POINT BEACH NUCLEAR PLANT On May 11,1979, 'he NRC staff met with representatives of Wisconsin Electric Power Company for a det led discussion of the auxiliary feedwater system at Point Beach t : lear Plant.

Attendees are listed in Attachment 1.

The meeting was a part of a larger scope task to consider what, if any, changes are required for non-8&W plants in light of the Three Mile Island Unit 2 experience. The material discussed is listed in Attachment 2.

The information gathered at this meeting will be included in an NRC staff report to the Commission.

It will include information generic to W plants and specific information. on Point Beach. The report will include any recommended changes the staff believes are needed and present conclusions as to whether or not continued operation is justified (all CE and W plants).

At the conclusion of the meeting, the information written by the staff with respect to this system was reviewed with the licensee.

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Charles M. Trammell, Project Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments:

1.

List of Attendees 2.

Material Discussed cc: w/ attachments 2345 329 See next page 79062003 N 8

LIST OF ATTENDEES POINT BEACH NUCLEAR PLANT May 11, 1979 MEETING WISCONSIN ELECTRIC POWER COMPANY NRC R. Newton W. LeFave F. Rhodes S. Asselin (Sandia)

C. Trammell 2345 430

'I ?ar cf its en-;;ing review of the Three "ile ~3'.and L' nit 2 a::i.:-,

h3 staff finds that it needs additional information regarding tna :.,.iliary ft d;.ater systems (AFUS).

This infcrmation as cutlined telew, is r::; ired to evaluate AFW5 reliability for Cembustion Engineering (CE) anc Westingneuse (W) designed pressurized water reactors.

The requested information is in additicn to that requested in the IE Bulletins, and should be brought to the maeting scheduled.ith the staff on May 8 thru May 12, 1979.

Written system description (as built) including:

List of Support Systems for Auxiliary Feed System Operation (Soth Electric and Steam)

Water Supplies for AFWS (primary and backup)

Current operating precedures and test and maintenance requirements including:

- All LCO's for AFWS, main FW system and related support systems.

Listing of operator actions (local and/or control recm; and timing re;uire-ments for such actions.

Procedures for reinitiating main feedwater ficw.

As Suilt P& ids with symbol keys including condensate and steam side Ledgible Equipment layouts drawings including:

Isemetrics, if available Identificati.cn of inhibits preventing accessibility to AFWS components and related electrical equipment Relevant control systems description including:

Schematic or logic control diagrams Listing of actuation signals / logic and control MSIS logic for isolating AFWS, if installed electric power dependences

.All " readouts" available in control room for AFWS cperation AC & DC Power One line diagrams (normal and emergency power supplies)

Divisional designation e.g., Train A, Train B, requirements en all AFWS components and support systems

, List of normal valve states and loss-of-actuation power failure positicn Operating Experience, including Number of main feedwater interruptions per year experienced to date for each unit Number of demands on AFWS per year to date (test and actual) for each unit Summary of AFWS malfunctions, problems, failures Provide Available reliability analyses Steam Ger.erator dry-cut times (assuming loss of ali feed..a:er ficw, with 100%

initial ; war, with Reacter trip, no line breaks)

Syster desicn bases includinc:

Seu-i: ind envir:nr. ental'qualificaticn 23 f]

^j } l Ccd2 and Quality, QA O

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rei:: ses :: th s fill:v,i'r; s e: cf :_titi:ns b C: scribe ba:Lup systems available (to auxiliary fc:d.;ater) f r ;reviding fied..ater to steam generators.

Discuss actions and time rc;uired to make these systems available. Are procedures available?

If so, pr:.ide.

Provide the following procedures:

loss of offsite pcwer loss of feedwater LOCA (small and large)

Steam Line Ereak Provide following information for POR"'s:

tiumber Capacity setpoints (open and close) manufacturer and model i

indications of position record of periods isolated (isolation valve shut) challenges during life of plant (from plant records) including performance of valve, cause of challenge.

experience of two-phase or subcooled discharge of PORVs and safety valves with description of valve perfcrmance Provide indications of PORY isolation valve in the control rocm.

Provide the folicwing infonr.ation on ECCS:

initiation setpoints system description pump performance characteristics (head curves)

Provide reactor protecticn system trip setpoints.

Provide information on charging pumps, how they re.l. ate to ECCS including:

number flow vs. pressure power sources and backup water sources seismic qualification List all challenges (and cause) to ECCS as indicated on plant records.

List and discuss all instances during which your plant has undergone natura' circulation.

Describe all aut matic and manual features which can t:0 the reactor s

cooiant pumps.

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.t Meeting Summary for Wisconsin Electric Power Company Occket Files NRC POR Local POR CRB1 Reading NRR Reading H. Denton E. Case V. Stello D. Eisenhut

8. Grimes R. Vollmer A. Schwencer D. Ziemann P. Check G. Lainas D. Davis B. Grimes T. Ippolito R. Reid V. Noonan G. Knighton D. Brinkman Project Manager OELD OI&E (3)

C. Parrish ACRS (16)

NRC Participants

. J,=3 hanan ERA L-f see Mr. Bruce Churchill, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

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.333 Washington, D. C.

20036 Document Department University of Wisconsin Stevens Point Library Stevens Point, Wisconsin 54481 Mr. Glenn A. Reed, Manager Point Beach Nuclear Plant Route 3, Box 48 Two Rivers, Wisconsin 54244