ML20196D996

Summary of 881129 Meeting W/Util to Discuss Open ATWS Issues at Facility in Attempt to Reach Agreement on Conceptual Design.List of Attendees,Agenda & Slides Encl

ML20196D996
Person / Time
Site:	Crystal River
Issue date:	12/07/1988
From:	Silver H Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8812090252
Download: ML20196D996 (19)

Text

,

t gP 8'pn n: k UNITED STATES

{ g NUCLEAR REGULATORY COMMISSION 3 l WASHINGTON, D. C. 20655

.. / December 7, 1988  ;

Docket No. 50-302 LICENSEE: Florica Power Corptration (FPC)

FACILITY: Crystal River Unit 2 (CR-3)

SUBJECT:

CRYSTAL RIVER UNIT 3 -

SUMMARY

OF !!0VEMBER 29, 1988 MEETING CN ANTICIPATED TPANSIENTS WITHOUT SCRAli (ATWS)

On November 29, 1988, representatives of FPC met with representatives of tl.e NRC staff to discuss open ATWS issues at CR-3 in an attempt to reach agreernent on the conceptual design. The list of attendees, agenda, and slides discussed curing the meeting are enclosed.

FPC presented a brief description of the Einergency Feedwater Initiation and Control (EFIC) system to clarify its functions Anni interfaces with ATWS. In response to a question, FPC stated that byoassing EFIC with the ATUS Mitigation System Actuation Circuitry (AMSAC) signal to initiate Emergency Feedwater (EFW) flow would violate NUREG-0737 require'nents for class 1E EFW initiation and control. Spurious AMSAC actuation Could endanger EFW control, possibly resulting in serious overcooling events. In total, such a design would not represent an increase in overall plant safety.

The issue of independence of ATWS f rom the Reactor Trip Systems (RTS) was discussed only briefly since this aspect of the conceptual design was essqntially resolved.

With regard to diversity, FPC stated that EFIC is separate and diverse from the Reactor Prutection System (RPS). The ATWS logic (Eciley S20) was described as different from the RTS logic (Bailey 880). FPC agreed to sLbmit additional schematics and descriptions to support this position as part of the final design abtwittal. For the conceptual design, presently submitted information is acceptable.

FPC also noted that the reactor coolant purp input to AMSAC is picked up directly from the pump power monitor upstream of any EFIC logic FPC will submit additional supporting information as part of the conceptual desigi). $

Isolation of ATWS from other systems was saic to be the same as the isolation used for the Safety Parameter Display System (SPOS) and Regulatory Guide 1.97 applications. As part of the conceptual design submittal, FPC will verify this, provide the snodel nunber and manufacturer of the isolators and state that their application in ATWS does not invalidate use of these isolators. Additional details will be presanted with the f anal design package, hRC representatives at the weeting stated that uther than receipt of the informa-tion stated above, there were no appirent problems with the ATWS conceptual design as now documented.

HRC requested that FPC expidite submittal of the final design package now scheduled for June 1989. FPC stated that this schedule represents full construction design information, which NRC stated was not required for our review. NRC agreed to r9 G912090252 GG1207 (\g PDR ADOCK 0500030'2 \

P PDC i

Mr. W. S.'Wilgus December 7,1988 i

review the submittal of November 22, 1988 and the information pertaining to the three additional items discussed above when submitted, to determine what, if any, additional information is required for our final design review. FPC agreed to provide the information related to the three items specified above within 2 weeks.

FFC agreed that it will continue to proceed with design and implementation of ATHS equipment by the next refueling.

ORIGINAL SIGNED BY Harley Silver, Project itanager Project Directorate 11-2 Division of Reactor Projects-l/11 Office of Nuclear Reactor Regulation

Enclosures:

1. Attendance List <

., 2. Agenda

3. Slides cc w/ enclosures:

j See next page

[HEETINGSUtWARY/C AlRIVER]

l M i L- 2 PMT I-2 NRR- D:P .

D er HSilver/jd St berry HB'e fo r 12/ /88 12/7/88 1/]/88 12/7 /88 i

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Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear

. Florida Power Corporation Generating Plant cc:

Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governcr P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee fir. F. Alex Griffin, Chairman Director, Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, clorida 36250 Mr. Robert B. Borsum Mr. E. C. Simpson Babcock & Wilcox Director, Nuclear Site Nuclear Power Generation Division Floi da Power Corporation Support 1NO Rockville Pike, Suite 525 P.O. Box 219 Rockville, Maryland 20852 Crystal River, Florida 32629 Resident Inspector U.S. Nuclear Regulatory Commission 15760 West Powerline Street Crystal River, Florida 32629 Regional Administrator, Region II U.S. Nuclear Regulatory Connission 101 Marietta Street li.W., Suite 2900 Atlanta, Gec gia 30323 Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 l

l Administrator Depart:wnt of Enviionmental Regulation Pwer Plant Siting Secti; a State nf Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304

]

ll ,-

ENCLOSURE 1 NRC-FPC MEETING ON ATWS FOR CR-3 November 29, 1988 NAMES ORGANIZATION Harley Silver NRR/PM Vincent Thomas NRR/ICSB f nat Collins INEL Jack Tunstill FPC Bert Simpson FPC Jerry L. Mauck NRR/ICSB Bob Stevens NRH/ICSB Richard low FPC Ken Wilson FPC Carl C. Strempke Gilbert Assoc. Inc.

Scott Newberry NRR/SICB Stu Long ACRS i

l l

_ . . . . . . . . . . _ _ _ _ _ _ . . _ _ _ _ _ . .._ _ _ _ _ Q

ENCLOSURE 2

.' i AGENDA NOVEMBER 29, 1988 o,

NRC/FPC ATW5 MEETING -

The purpose of this meeting is to resolve all open ATWS mitigation design issues. Both NRC and FPC have benefit of 11/18 RAI and 11/22 FPC submittal and should be able to clearly understand any remaining differences or misunderstandings. Outcome should be means to document sufficient final closure to support FPC design and installation by Refuel 7.

I. Introduction II. EFIC Design Overview III. Discussion of Key Issues A. Independence B. Diversity C. Isolation D. EFIC Interface IV. Resolution of key issues A. Closed by FPC 11/22 Submittal B. Closed by FPC 11/22 Submittal and Final Design C. Closed by FPC 11/22 Submittal and Final Design D. Resolved at meeting V. Discussion of Final Documentation of NRC Acceptance of Conceptual Design 4

l

'. 4 'U ENCLOSURE 3 EFIC OVERVIEW

l. INTRODUCTION

11. OVERVIEW OF CHANNELS '

a. channels A,B,C,&D ----slides 1,2,3,4,

1. Inpute. -

2. Initiate & trip outputs

3. actuation logic

, Ill. INiiIATION MODULE

a. logic----slide 5

b. schematic (partial)-- --slide 6 .

1. RCP eptic isolators

2. FW Inpt'ts OR gates IV. AMSAC INTERFACE j a. A,B,C.& D overview, gal dwg ------sildes 7,8,9,10

b. FP' ' tv, -----slide 11 c protectior nodule -----slide 12 V. QUESTIONS t

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DISTRIBUTION FOR MEETING

SUMMARY

DATED: ,

3 ..

Facility: Crystal River Unit 3 I C05that' f'tle19 .

NRC & Local PDRs  :

PDII-2 Reading ,

S. Varga, 14-E-4 r G. Lainas, 14-H,3 i H. Berkow D. Miller f H. Silver  !

OGC-WF 15-B-18 i E. Jordan HNBB-3302 i NRC Participants i i

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