ML19259D600

Summary of 791009 Meeting W/Util Re Proposed Steamline Break Protection

ML19259D600
Person / Time
Site:	Beaver Valley
Issue date:	10/18/1979
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-11010, NUDOCS 7910250152
Download: ML19259D600 (30)

Text

{{#Wiki_filter:/52A .t 8[ ),, + UNITED STATES +, g N ; CLEAR REGULATORY COMMISSION 5 ej WASHINGTON, D. C. 20555 OCTURER 13 1979 Docket No.: 50-334 LICENSEE: Duquesne Light Company FACILITY: Beaver Valley, Unit No.1

SUBJECT:

MEETING

SUMMARY

- STEAMLINE BREAK PROTECTION SYSTEM The licensee and their nuclear steam supply system vendor, Westinghouse, met with the staff on October 9,1979 to discuss the proposed steamline brr* protection system (SLBPS) for the Beaver Valley Power Station, Unit No... The list of meeting attendees is enclosed.

Westinghouse (D. Wood) discussed the details of the proposed design and the steamline break analysis using the agenda and vugraphs attached. Emphasis was placed on the system functions and plant behavior for credible steamline breaks while in the heatup or cooldown mode. W used a plant status and single failure type flow chart to show that most steamline breaks do not result in the pressurizer level being lost nor does the reactor coolant system pressure reach a saturation condition. For those break sizes and locations where pressurizer level is lost and/or saturation (inditions are reached, W stated that: (1) the time intervals are quite long (about 20 minutes) aiid numerous alarms are available to alert the operator to the situation, (2) the operator's corrective action would be a simple act (initiate SIS), (3) the initial conditions that were assumed are extremely conservative and may be impossible without first having violated equipment and/or operating limitations and (4) the assumed single failure (loss of normal charging) while possible, would not be likely since a cooldown or heatup operation requires diligent operator attention to the status of the Charging and Volumn Control System (CVCS), and there are numerous means of a:;suring continuous charging flow. Following the presentation by the licensee and Westinghouse, the staff requested that the information provided be formally docketed by the licensee. Included would be the assumptions used in the analyses and the conclusions drawn from the results of the analyses. 1213 303 f 910 2 5 0 l s z-

's . OCTOBER 18 1979 The staff indicated its conceptual approval of the proposed new SLBPS based on the information submitted to date and the analyses Westinghouse (W) presented at the October 10, 1979 meeting. However, final NRC approval oT the SLBPS is contingent on our receipt and review of (1) the information W presented at the 10/10/79 meeting, (2) specific Technical Specifications requiring the RCS to be borated to the cold shutdown requirements before placing the SLBPS in the cooldown/heatup mode and (3) satisfactory review of the SLBPS instrumentation and control aspects (to be performed by RSB). ,i Dave Wigginto roject Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments: 1. Peeting Attendees 2. Agenda 3. Vugraphs 1213 304

Meeting Summary for UCIUBER 16 1979 Beaver Valley Docket Files Gerald Charnoff, Esquire NRC PDR Jay E. Silterg, Esquire Local PDR Shaw, Pittman, Potts and Trowbridge ORB 1 Readin9 1800 M Street, N.W. NRR Readin9 Washington, D. C. 20036 H. Denton E. Case Karin Carter, Esquire D. Eisenhut Special Assistant Attorney General G. Zech Bureau of Administrative Enforcement B. Grimes 5th Floor, Executive House W. Gammill Harrisburg, Pennsylvania 17120 L. Shao J. Miller Mr. Roger Tapan R. Vollner Stone and Webster Engineering T. J. Carter Corpe"ation A. Schwencer P. 0. Box 2325 D. Ziemann Boston, Massachusetts 02107 P. Check G. Lainas Mr. J. D. Woodward D. Davis R & D Center B. Grimes Westinghouse Electric Corporation T. Ippolito Building 7-303 R. Reid Pittsburgh, Pennsylvania 15230 V. Noonan D. Crutchfield B. F. Jones Memorial Library G. Knighton 663 Franklin Avenue D. Brinkman Aliquippa, Pennsylvania 15001 Project Manager DELD Mr. Jack Carey OISE (3) Technical Assistant C. Parrish/P. Kreutzc? Duquesne Light Company ACRS (16) P. O. Box 4 NRC Pa-ticipants Shippingport, Pennsylvania 15077 J. Buchanan TERA Mr. R. E. Martin Licensee Duquesne Light Company Mr. Janes A. Werling 435 Sixth Avenue Plant Superintendent Pittsburgh, Pennsylvania 15219 Beaver Valley Power Station P. O. Box 4 Marvin Fein Shippingport, Pennsylvania 15077 Utility Counsel City of Pittsburgh Mr. John A. Levin 313 City-County Building Public Utility Commission Pittsburgh, Pennsylvania 15219 P. O. Box 3265 Harrisburg, Pennsylvania 17120 1213 305

ATTENDANCE 10/9/79 MEETING DUQUESNE LIGHT COMPANY BEAVER VALLEY PLANT TIME: 10:30 a.m. ROOM: P-130A NRC E. A. Reeves NRR/ DOR /0RB #1 S. Salah NRR/ DSS /AB L. B. Ma rsh NRR/ DOR R. Lobel NRR/ DOR /RSB F. Orr NRR/ DSS /RSB C. M. Berlinger NRR/ DOR /RSB DLC J. J. Carey Others Dennis Gregg }f, NSD Projects Bob Steitler W Doug Wood H 1213 306

s i /u-1-29 AGfNDA SYSTEM DESCRIPTION DESIGN BASIS PROTECTION SYSTEM RESPONSE STEAMLINE ISOLATION SAFETY INJECTION TOTAL SYSTEM RESPONSE - ANALYSIS RESilLTS 1213 307 e e

s DESIGN BASIS CONDITION II (STEAM DUMP, STEAM GENERATOR RELIEF OR SAFETY VALVE FAILURE) DOSE LIMITS PRECLUDE FUEL DAMAGE CONDITION IV (LARGE BREAKS) MEET 10CFR100 DOSE LIMITS CORE REMAINS IN C00LABLE GE0MFTRY 1213 303

MIGH LO W TEAMLINE PRE 550R12ER STE INE 5t M INE CON IN ENT AtG DiFFERENil AL PRESSURE PRE 55URE PRE 450RE FLOW Pile S SUR E h 9r 1r 1r AND AND 0 av M i - 2. BLOCKED DURING NEATUP AND CONT AINNENT C00 m PRES $URE ir 1r 1r 1r 1r u i r STEAMLINF ] M ISOLATION lllJICllON Prese Steamline Break Protection System (USED O!'lY DUiilNG) B_OCKED DURil5 HEATilP NORMAL C00LD0'.N AND E AND C00LDGf4 HEATUPOPERATIONS) rm afe' H I -2. HIGH LOW gy Hi-l CONTAihMENT STEAMLINF STEAMLINE PRESSURilER CONTAthMEN[ PRESSURE PRESSURE PP'SSURE PRESSURE PRESSURE RATE t, Wh STEAMLINE SAFETY 1215 ,09 Ibulail0N INJECTION ) New Steamline Break Protection System

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STEAMLINE BREAK PROTECTION HEATUP/C00LDOWN STEAMLINE ISOLATION PROVIDES PRIMARY PROTECTIVE FUNCTION TERMINATES BLOWDOWN 5 0UTSIDE DECREASES BLOWDOWN RATE FOR BREAKS INSIDE REACTOR CONTAINMENT PROVIDED BY HIGH STEAM PRESSURE RATE SIGNAL BLOCKED ON LOW STEAMLINE PRESSURE SAFETY INJECTION ?R0VIDES ADDITIONAL SHUTDOWN REACTIVITY VIA CONCENTRATED BORON INJECTION PROVIDES WATER 'O RCS PROVIDED BY HI-l CONTAINMENT PRESSURE BLOCKED ON LOW PRESSURIZER PRESSURE AND ON LOW STEAM PRESSURE 1213 317 e

UNDER WHAT CONDITIONS ARE THESE SUBSYSTEMS NECESSARY UNNECESSARY UNDESIREABLE 121.5 ji8

OPERATI0tlAL C0flSIDERATIONS - SPURIOUS STEAMLIrlE ISOLATION DURING C00LDOWN - SPURIOUS SAFETY INJECTION DURING C00LDOWN SAFETY CONSIDERATIONS - STEAMLINE ISOLATION TO TERMINATE LARGE SUSTAINED BLOWDOWNS - SAFETY IfiJECTION TO PROVIDE RCS INVEtiTORY TO COMPENSATE FOR C0OLANT SHRINKAGE 1213 319

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m n ~ S -~ TIME (SEC) ~ . INITI AL PRESSURF 79 BREAK SIZE .2 SQ FT PER LOOP N3 CHARGING ASStr'.ED ACClFiULATORS RLOCKED 1213 331 ?00R ORGINAL

CONCLUSI0t;S FOR "AT POWER CASES, NEW STEAMLINE BREAK PROTECTION PROVIDES EQUIVALENT PROTECTION AS PRESENT SYSTEM. THERE ARE DIFFERENCES IN SYSTEM RESPONSE WHILE PLANT IS IN THE HEATUP/C00LDOWN MODE. WITH CHARGING FLOW AVAILABLE, THE PRESSURIZER DOES NOT EMPTY FOR BREAKS NOT ISOLATED BY PRESSURE RATE. OPERATOR HAS IN EXCESS OF 30 MINUTES TO ?NITIATE SAFETY INJECTION PRIOR TO SATURATION IN THOSE REMOTE CASES WHERE THE POTENTIAL EXISTS FOR REACHING SATURATION. THE NEW STEAMLINE BREAK PROTECTION SYSTEM MEETS THE DESIGN CRITERIA. 1213 332 .}}