ML19316A522

Notification of 760708 Meeting W/Util in Bethesda,Md to Discuss Causes & Prevention of PWR Reactor Vessel Overpressurization Events.Agenda Encl

ML19316A522
Person / Time
Site:	Oconee
Issue date:	07/02/1976
From:	Zech G Office of Nuclear Reactor Regulation
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 7912300063
Download: ML19316A522 (5)

Text

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JUL 2 1976 DISTRIBtrrION:

Docket Files (3) [

ORBf1 Reading NRR Reading Dockets Nos. S Q /270/287 Albert Schwencer, Cnief, Operating Reactors Branch #1, DOR FORTilCOMING MEETING WITH DUKE POWER COMPANY (CCONEE NiJCI. EAR STATION)

Date and Time:

July 8,1976 Thursday 9:45 a.m.

Incation:

Phillips Building Room 316-B

Purpose:

To discuss causes and prevention of PWR reactor vessel overpressureration events.

(See ai:tached agenda)

Participants:

Duke Power Company M. "Aackman, et al NRC C. Berlinger R. Fluog;c R. Ga.%1e C. G. Zech, et al Original signed by Gary C. Zech, Project Manager Operating Reactors Branch #1 Division of Operating Reactors

Enclosure:

Agenda cc w/ enc 1:

See next page orrecE W 50R:0RBf1 eune.ame >

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7/ilA persa ABC 313 (Rev.9 53) A5'38 3240 W u. s. oovERNMENT PR6MT6MG oPFSCEE to74*gte-tee

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. July 2, 1976 Meeting Notice for Duke Powtr T

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G. Knighton cc: NRC PDR B. Youngblood Local PDR W. Regan B. Rusche D. Bunch E. Case J. Collins R. Boyd W. Kreger R. !!cineman R. Ballard i

V. Stello M. Spangler H. Denton J. Stepp l

D. Skovholt L. Hulman R. Denise T. Carter R. DeYoung OR PM R. Maccary S. Sheppard D. Ross R. Fraley, ACRS(16) 1 R. Tedesco SD(3)

I K. Coller OISE(3)

D."Eisenhut OELD V. Moore B. Faulkenberry, OISE R. Vollmer Receptionist M. Ernst Principal Staff Participants W. Gammill P. Collins T. B. Abernathy, TIC bec:

C. Helten s J. R. Buchanan, NSIC R. Houston T. Speis Dudley Thompson, Acting Director R. Clark Division of Field Operations J. Stolz Office of Inspection and Enforcement K. Kniel Mail Stop 359 E/U O. Parr W. Butler D. Vassallo' J. Knight S. Pawlicki I. Sihweil l

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P. Check T. Novak

2. Rosztoczy V. Benaroya G. Lainas T. Ippolito D. Ziemann G. Lear R. Reid L. Shao R. Baer A. Schwencer B. Grimes m.

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Agenda for Meeting to Discuss Reactor Vessel Overpressurization Events STAFF PRESENTATION Statement of Problem Sigr.ificance of Problem Definition / Statement of Acceptance Criteria Long Term Fix Design Modifications to Prevent Overpressure Transients Mitigate Consequences Interim Fix t

- Reduction of Likelihood

- Mitigate Consequences LICENSEE PRESENTATION Past History Identify Overpressure Incidents

- Evaluate Susceptibility of Plant to Overpressure of RCS

- Quantify Occasions of Water Solid and/or Cold Shutdown Operation Design / Procedural Modifications to Prevent Reoccurrence

- Discuss Success / Failures of Fixes Pressurizer Relief Valve Performance Parameters

- Valve Cycle Times

- Control Logic

- Range / Accuracy of Wide Range Pressure Sensors l

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I LICENSEE PRESENTATION _ (continued)

Pressurizer Relief Valve Performance Parameters (cont) j f

Display Instrumentation and Alarms Assessment of Possibility of Operating Plant Without Being Water Solid Discuss Capability of Providing and Controlling a Nitrogen Blanket GENERAL DISCUSSION _

i Interim and Long Term Fixes 4

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i Infornction to be Provided to NRC at the Meeting 4 copies of large sized P&ID's charging, letdown, RHR and reactor coolant systems Viewgraphs of System PGID's for use in discussion

- 4 copies of operating procedures for operations during cold shutdown and water solid conditions

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Fluence Data Capsules removed Removal schedule for future Copy of NSSS Surveillance Program Data on hand not yet submitted i

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