ML20058L983

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Summary of 930811 Meeting W/Utils & Vendors in Rockville Re FPC Justification for Use of non-App G Methodolgy for LTOP Protection at Crystal River Unit 3.List of Attendees Encl
ML20058L983
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/13/1993
From: Silver H
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9312200091
Download: ML20058L983 (15)


Text

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December 13, 1993 Docket No. 50-302 LICENSEE: Florida Power Corporation (FPC)

FACILITY: Crystal River Unit 3 (CR-3)

SUBJECT:

SUMMARY

OF MEETING ON AUGUST 11, 1993 - REGARDING LTOP PROTECTION Representatives of the licensee met with members of the staff on August 11, 1993, in Rockville, Maryland, to discuss FPC's justification for the use of non-Appendix G methodology for LTOP protection at CR-3.

Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the licensee's agenda and handouts used at the meeting.

Areas of concern expressed by the staff included: history of LTOP events and-precursors at CR-3 and other B&W plants; justification that one PORV and operator action with a steam bubble in the pressurizer constitute a single-failure-proof LTOP system; and explanation as to why Appendix G or Code case methodology is not adequate for the licensee. The licensee addressed these concerns in its presentation, but the staff needed to consider further whether an LTOP event could be considered as not being expected to occur during the life of the plant, and whether the CR-3 LTOP system could be considered single-failure proof. This review is continuing.

(Original Signed By)

Harley Silver, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II

Enclosures:

As stated cc w/ enclosures:

See next page

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1 Docket No. 50-302 >!

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i LICENSEE: Florida Power Corporation (FPC)  !

i FACILITY: Crystal River Unit 3 (CR-3) l

SUBJECT:

SUMMARY

OF MEETING ON AUGUST 11, 1993 - REGARDING LTOP. PROTECTION l

3 Representatives of the: licensee met with members of the staff on August 11,-

1993, in Rockville, Maryland, to discuss FPC's justification for the use of l

i non-Appendix G methodology for LTOP. protection at CR-3.  ;

Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the licensee's  !

agenda and handouts used at the meeting. J

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Areas of concern expressed by the staff included: history of LTOP eventsLand 'i precursors at CR-3 and other B&W plants; justification that one PORV and i operator action with a steam bubble in the pressurizer constitute a single-failure-proof LTOP system; and explanation as to why Appendix G cr Code case'  ;

methodology is not adequate for the licensee. The licensee addressed these '

concerns in its presentation, but the staff needed to consider further whether~  !

an LTOP event could be considered as not being expected to occur during the  :

life of the plant, and whether the CR-3 LTOP system could be considered '

single-failure proof. This review is continuing.  :

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Harley 1 er, Sr. Project Manager  !

Proj t Directorate 11-2 i DivsidofReactorProjects-I/II ,

Enclosures:

As stated  !

v cc w/ enclosures-See next page .

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- Crystal River Unit No.3 Florida Power Corporation Generating Plant cc:  ;

- Mr. Gerald'A. Williams Mr. Joe Myers, Director a Corporate Counsel Div. of Emergency Preparedness l Florida Power Corporation Department of Comunity Affairs  !

MAC-ASA 2740 Centerview Drive i P. O. Box 14042 Tallahassee, Florida 32399-2100 St. Petersburg, Florida 33733 Mr. Bruce J. Hickle, Director Chairman Nuclear Plant Operations (NA20) Board of County Comissioners Florida Power Corporation Citrus County Crystal River Energy Complex 110 North Apopka Avenue-15760 W. Power Line Street Inverness, Florida 32650 +

Crystal River, Florida 34428-6708 Mr. Robert B. Borsum Mr. Rolf C. Widell, Director 4

- B&W Nuclear Technologies Nuclear Operations Site Support (NA21) i 1700 Rockville Pike, Suite 525 Florida Power Corporation Rockville, Maryland 20852 Crystal River Energy Complex .'[

15760 W Power Line Street '

Crystal River, Florida 34428-6708 Regional Administrator, Region II i U. S. Nuclear Regulatory Comission Senior Resident Inspector  :

101 Marietta Street N.W., Suite 2900 Crystal River Unit 3 l Atlanta, Georgia 30323 U.S. Nuclear Regulatory  :

Comission  !

Mr. Bill Passetti 6745 N. Tallahassee Road 1 Office of Radiation Control Crystal River, Florida 34428  !

Department of Health and ,

Rehabilitative Services Mr. Gary Boldt i 1317 Winewood Blvd. Vice President - Nuclear '

Tallahassee, Florida 32399-0700 Production (SA2C) ,

Florida Power Corporation Attorney General Crystal River Energy Complex  !

Department of Legal Affairs 15760 W Power Line Street  !

The Capitol Crystal River, Florida 34428-6708 i Tallahaseee, Florida 32304 '

Mr. Percy M. Beard, Jr. -

Sr. Vice President  ;

Nuclear Operations i Florida Power Corporation i ATTN: Manager, Nuclear Licensing (NA21)  ;

Crystal River Energy Complex  !

15760 W Power Line Street  !

Crystal River, Florida 34428-6708 )

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Enclosure 1 Crystal River Unit 3 LTOP Meeting August 11,1993-Attendees l

Rang Office Harley Silver NRR/PDII-2 Barry Elliot NRR/EMCB Jack Strosnider NRR/EMCB Keith Wichman NRR/EMCB Chris Grimes NRR/0TSB Rolf Widell FPC Ken Wilson FPC l Ronnie Lo NRR/0TSB l Herb Berkow NRR/PDII-2 l Tim Collins NRR/SRXB Bob Borsum BWNT L. Zerr STS/EPRI Ed Hackett NRR/EMCB John Tsao NRR/EMCB LRaghavan NRR/PDII-2 Richard Croteau NRR/PDII-2 Robert DePriest NRR/PDII-2 Lambros Lois NRR/DSSA/SRXB Ken Yoon BWNT Robert Enzinna BWNT

. David Miskiewicz FPC Blair Wunderly FPC Jim Andrachek Westinghouse Darrell Gardner TVA/ Watts Bar Tom Porter TVA/WBN Licensing Bob Jones (Part Time) NRR/SRXB

1 Enclosure 2 I I

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AGENDA FOR CR-3 LTOP Meeting .

1

1. Review prior licensee commitments for CR-3 LTOP analysis.
2. Review justification for considering LTOP events as non-anticipated operational occurrences at CR-3.

l

3. Compare fracture mechanics criteria and pressure-temperature limits for:
a. ASME Code, Appendix G methodology
b. Code Case N514 methodology
c. Licensee's proposed methodology ,
4. Compare LTOP setpoints, enabling temperatures and operating windows using:
a. ASME Code, Appendix G and SRP 5.2.2 methodology ,
b. Code Case N514 methodology
c. Licensee's proposed methodology
5. Summary:
a. Bases of proposed fract. mech. criteria for LTOP limit curves

l B&W LTOP EVENT FREQUENCY i

OBJECTIVE LTOP EVENTS THAT EXCEED APPENDIX G P/T LIMITS ARE NOT ANTICIPATED OPERATIONAL OCCURRENCES FOR B&W PLANTS BACKGROUND NUREG-1326 (REGULATORY ANALYSIS OF GI-94, 1989):

"THE B&W PLANTS HAVE BEEN EXCLUDED FROM THIS EVALUATION BECAUSE THESE UNITS HAVE NOT EXPERIENCED ANY LTOP TRANSIENTS AND, BASED ON THEORETICAL RISK, DO NOT CONTRIBUTE TO THE OVERALL RISK 0F LTOP EVENTS."

HUREG/CR-5186 (VALUE IMPACT ANALYSIS OF GI-94, 1988): ,

8 AT B&W PLANTS DURING 1980 TO 1986, THERE WERE NO EVENTS THAT CHALLENGED THE OVERPRESSURE MITIGATION SYSTEM HARDWARE (RELIEF VALVE) e BASED ON OPERATING EXPERIENCE DURING 1980 TO 1986, HUREG/CR-5186 PREDICTS LESS THAN 0.0016 OVERPRESSURIZATIONS PER REACTOR YEAR FOR PORV-AND-BUBBLE CATEGORY (B&W) PLANTS REVIEW 0F B&W OPERATING HISTORY 4 INVESTIGATED B&W EXPERIENCE OF POTENTIAL CHALLENGES TO LTOP SETP0INTS e CONFIRMED THAT OPERATING EXPERIENCE SUPPORTS THE RESULTS OF NUREG/CR-5186 (I.E LTOP IS NOT AN ANTICIPATED OPERATIONAL OCCURRENCE FOR B&W PLANTS)

FRACTURE MECHANICS BASES FOR LTOP SET POINT K. K. YOON B&W NUCLEAR TECHNOLOGIES Lynchburg, Virginia FOR FLORIDA POWER CORPORATION August 11,1993

., .., ,.-,-, ,, .,,_._,,..---..,-cu . . ,+ , , . - ,, -.w.- . . . - . .,,%,. - . , - w - y . -oms - r.. - . . , , y.,,. . ..m- .e,

1 CODE CASE N-514 AND REVISED APP. G, SECTION XI .

(LEVEL A & B LTOP) l-l o LTOP SET POINT - 110% OF TECH SPEC APPENDIX G LIMIT o ENABLE TEMPERATURE - RTNDT + 50 F OR 200 F WHICHEVER IS GREATER

7 FRACTURE MECHANICS BASIS FOR ,

TECHNICAL SPECIFICATION APPENDIX G LIMIT i

i o . FLAW SIZE - REFERENCE FLAW (t/4) i l -o FRACTURE TOUGHNESS - KIR CURVE I o SAFETY FACTOR - 2 ON PRIMARY LOAD i

l o LTOP IS AN ISOTHERMAL TRANSIENT l

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l' FRACTURE MECHANICS ANALYSIS FOR LEVELS A & B VERSUS C SERVICE LOADS SERVICE LEVEL A AND B C FACTOR FLAW DEPTH t/4 t/10 V10/4=1.58 TOUGHNESS KIR KIc > 1.2 S.F ON PRIMARY 2 1.4 2/1.4= 1.4 STRESS ACCUMULATED SAFETY FACTOR OVER 2.65 TECH. SPEC. APP. G LIMIT

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FRACTURE MECHANICS BASIS SERVICE LEVEL A AND B 0 tiler B&W FACTOR LTOP FLAW DEPTH t/4 t/4 1 TOUGHNESS KIR KIR 1 S.F ON PRIMARY 2 1 2 STRESS ACCUMULATED SAFETY FACTOR OVER 2.0 TECH. SPEC. APP. G LIMIT 6

_____--____m___-- -_ __ __ m . . . , , e-i. --e . . . . . . --3 -=,- , = ==.,,.--.-e . .--- +- e - e--,-, - .-w-.

r LTOP SET POINT FOR CR-3 o LTOP SET POINT - 250% OF TECH SPEC APPENDIX G-LIMIT o ENABLE TEMPERATURE - RTNDT + 50 F OR 200 F WHICHEVER IS GREATER

. _ . ~ _ _ _ . . . _ _ _ . _ . _ _ . . _ _ . _ _ _ . _ . _. .. - . . _ . . . _ . - - - . , . . . . _ . . . . . . . . . - ..- .._ .._.. __. _ . _. - - _ . _ - . _ . _ _ _ _ _ _ _ . . . _ .

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MEMORANDUM DATED:

Distribution Docket File NRC & Local PDRs PDII-2 Reading T. Murley/F. Miraglia 12-G-18 J. Callan, 12-G-18 SVarga >

Glainas HBerkow HSilver RCroteau ETana OGC EJordan BElliott, 7-D-4 JStrosnider, 7-D-4 KWichman, 7-D-4 CGrimes, 11-E-22 RLo, ll-E-22 TCollins, 8-E-23 EHackett, 7-D-4 JTsao, 7-D-4 Llois, 8-E-23 BJones, 8-E-23 L. Plisco, ED0 RII MSinkule, RII 160031

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