ML20058H035
| ML20058H035 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/08/1993 |
| From: | Bevan R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9312100238 | |
| Download: ML20058H035 (22) | |
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UNITED STATES E
E NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20E0001 s
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December 8, 1993 Docket No. 50-368 i
LICENSEE: Entergy Operations, Inc.
FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)
SUBJECT:
SUMMARY
OF MEETING ON AUGUST 30, 1993, REGARDING CONTINUED OPERATION OF ANO-2 UNTIL THE NEXT SCHEDULED REFUELING OUTAGE On August 30, 1993, representatives of Entergy Operations, Inc. (the licensee), met with the NRC staff to present their case for continuing to operate ANO-2 without a steam generator (SG) examination until the next scheduled refueling outage in March 1994. Meeting attendees are. listed in.
A selection of materials handed out by the licensee is given in.
The licensee discussed the results of their most recent (spring 1993) SG examination, which encompassed 100% of all areas of concern. All detectable indications found were repaired. An evaluation by the licensee indicated that, after the inspection, no flaws were left that would exceed the RG 1.121 acceptance criteria. A conservative analysis showed that in a worst-case scenario the offsite dose consequences of a tube rupture event are within the 10 CFR Part 100 limits. Currently, 2.1% of the tubes in SG A and 3.1% of the tubes in SG B are plugged. The current safety analysis assumes a 5% plugging limit.
The licensee described current and future compensating measures to ensure continued safe operation for the remainder of the current operating cycle.
These include enhanced leak rate monitoring (N-16 monitors), improved water chemistry control, reduced hot-leg temperature, and operator training on SG tube rupture events. A risk assessment indicates a low risk associated with continued operation until spring 1994.
At the end of the meeting the licensee was told that the staff would get back to them regarding continued operation until the March 1994 outage.
Subsequently, the NRC concluded that, based on the low overall risk associated with continued operation, the additional training in handling operational 090008 931210023B 931208 I
PDR ADOCK 05000368 i
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occurrences, and the other enhancements, the unit could continue to operate until the next scheduled refueling outage in March 1994 with no undue risk to the public health and safety.
The licensee was so informed.
ORIGINAL S1GNED BY:
Roby B. Bevan, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
1.
Meeting Attendees 2.
Licensee's Handout cc w/ Enclosure 1:
See next page DISTRIBUTION w/ Enclosures 1 and 2:
Docket File NRC & Local PDRs PD4-1 P.eading R. Bevan T. Alexion A. B. Beach, RIV w/ Enclosure 1:
T. Hurley/F. Miraglia L. J. Callan J. Roe E. Adensam W. Beckner P. Noonan A. Thadani OGC E. Jordan NRC Participants ACRS (10)
J. Mitchell, EDO
- See previous concurrence OFC LA:PD4-T %'
PM:PD44 EMCB D:PD4.1 A NAME PNoonkn[
RBeNnYpI JStrosnider*
WBeckner DATE
}3/3/93 I3-/'7/93 12/03/93 1 - / 42 / 9 3 1
COPY YES[N0' YES/NO YES/NO YES/NO OfflCIAL RECORD COPY Document Name: AR2.AUG30.hlS
occurrences, and the other enhancements, the unit could continue to-operate until the next scheduled refueling outage in March 1994 with no undue risk to the public health an" safety. The licensee was so informed.
j, Roby B.
evan, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
1.
Meeting Attendees 2.
Licensee's Handout cc w/ Enclosure 1:
See next page
r s.
- occurrences, and the other enhancements, the unit could continue to operate until the next scheduled refueling outage in March 1994 with no undue risk to the public health and safety.
The licensee was so informed.
ORIGINAL SIGNED BY:
Roby B. Bevan, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
1.
Meeting Attendees 2.
Licensee's Handout cc w/ Enclosure 1:
See next page DISTRIBUTION w/ Enclosures 1 anri_2:
Docket file NRC & Local PDRs PD4-1 Reading R. Bevan T. Alexion A. B. Beach, RIV w/ Enclosure 1:
T. Murley/F. Miraglia L. J. Callan J. Roe E. Adensam W, Beckner P. Noonan A. Thadani OGC E. Jordan NRC Participants ACRS (10)
J. Mitchell, ED0
- See previous concurrence OFC LA:PD4-l w PM:PD44 EMCB D:PD4 1 a s NAME PNooniin)'
RBeNnp$
JStrosnider*
WBeckn r 13 } /93
$/7/93 12/03/93
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COPY YES/N07 YES/NO YES/NO YES/N0 OfFICIALRECORDCYPY Document Name: AR2.AUG30.MTS
Entergy Operations, Inc.
Arkansas Nuclear One, Unit 2 cc:
Mr. Harry W. Keiser, Executive Vice Mr. Jerrold G. Dewease President & Chief Operating Officer Vice President, Operations Support Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, Mississippi 39286 Jackson, Mississippi 39286 Mr. Charles B. Brinkman, Manager Mr. Robert B. McGehee Washington Nuclear Operations Wise, Carter, Child & Caraway ABB Combustion Engineering P. O. Box 651 Nuclear Power Jackson, Mississippi 39286 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Admiral Kinnaird R. McKee, USN (Ret) 214 South Morris Street Mr. Nicholas S. Reynolds Oxford, Maryland 21654 Winston & Strawn 1400 L Street, N.W.
Mr. Jerry W. Yelverton Washington, D.C.
20005-3502 Vice President, Operations ANO Entergy Operations, Inc.
Mr. Robert B. Borsum Route 3 Box 137G Licensing Representative Russellville, Arkansas 72801 B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852 i
Senior Resident Inspector U.S. Nuclear Regulatory Commission 1 Nuclear Plant Road Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable C. Doug Luningham County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Hs. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72205-3867
c ENCLOSURE 1 Auoust 30. 1993 Steam Generator Meetina Arkansas Nuclear One. Unit 2 List of Attendees Roby Bevan NRC/NRR/PD4-1 B. D. Liaw NRC/NRR/DE E. G. Adensam NRC/NRR/DRPW H. Rood NRR/DRPW Cliff Eubanks Entergy/AND Randall K. Edington Entergy/ANO Jerald Head Entergy/ANO Jerry Yelverton Entergy/ANO James Fisicaro Entergy/AND Emmett Murphy NRC/NRR/EMCB Jack Strosnider NRC/NRR/EMCB Richard S. Maurer ABB-Combustion Engineering Sterling Weems MPR William C McKelvy Entergy/ANO Joseph Donoghue NRC/NRR/DSSA/SRXB Ken Karwoski NRR/NRR/EMCB Dale James Entergy Tim Reed NRC/ Reactor Projects Lynn Connor STS Jeff Winton NRC/NRR/EMCB Craig Smith Baltimore Gas and Electric Bill Eaton Entergy/ANO Robert C. Jones NRC/NRR/SRXB t
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ENCLOSURE 2 J
J AGENDA J
STEAM GENERATOR MEETING 3
AUGUST 30,1993 J
I.
INTRODUCTION J. FISICARO II.
OPENING REMARKS R. EDINGTON III.
OVERVIEW C. EUBANKS
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IV.
TECHNICAL EVALUATION D. HARRISON
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V.
SAFETY ASSESSMENT J. HEAD
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VI.
OPERATIONAL RESPONSE R. EDINGTON VII. ENHANCEMENTS R. EDINGTON VIII. 2R10 INSPECTION SCOPE C. EUBANKS 3
i IX.
CONCLUSIONS R. EDINGTON
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- y CUMULATIVE REPAIR STATUS
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NUMBER PLUGS 158 255 NUMBER SLEEVES 388 56
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SLEEVE EQUIVALENT PLUGS 22 4
TOTAL TUBES PLUGGED 180 259 T.
PERCENT PLUGGED 2.14 %
3.08 %
DEFECT LOCATION CAUSING REPAIR SG "A" SG "B" J
EXPANSION TRANSITION 463 70 EGGCRATE SUPPORTS 30 147 BATWING SUPPORTS 10 46 SLUDGE PILE 31 19 PRESERVICE 15 29 pq G
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INSPECTION TECHNIQUE USED g
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INSPECTION OF 100% OF BOTH HOT LEGS g
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TESTING S PERFORMED USING SAhE l
PARAMETERS AS USED AT MAINE YANKEE, l
MILLSTONE, AND ST. LUCIE j
FREQUENCIES CALIBRATION STANDARDS
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PROBE TYPE j
UPGRADED ECT ANALYSIS GUIDELINES AND TRAINING / TESTING PROGRAM IMPROVES
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QUALITY OF DATA
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NRC TEAM INSPECTION YIELDED FAVORABLE COMMENTS ABOUT OUR PROGRAM IMPROVED DATA QUALITY OPTICAL ACQUISITION ANALYSTS TRAINED TO RECOGNIZE EXCESSIVE NOISE NOISE EXAMPLES IN GUIDELINES 3
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CIRCUMFERENTIAL CRACKING-EVALUATION I
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DISTRIBl) TION OF FLAW SIZE IS NOT
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WERE FOUND DURING FIRST " CIRC CRACK OUTAGE" l
LARGEST CIRC CRACK FOUND DURING SUCCESSIVE OUTAGES TENDS TO I
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NO CRACK IS EXPECTED TO BE PRESENT DURING 2R10 THAT EXCEEDS REG GUIDE 1.121 LIMITS, WITH A GREATER THAN 95% CONFIDENCE-LEVEL d
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. VALID EOP GUIDANCE
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. ACCEPTABLE OFFSITE DOSE CONSEQUENCES
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. ADEQUATE REFUELING WATER TANK (RWT)
J-INVENTORY
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FOR THE FOLLOWING EVENTS:
5 STEAM GENERATOR TUBE RUPTURE (SGTR) -
l SINGLE TUBE STEAM GENERATOR TUBE RUPTURE (SGTR) -
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MAIN STEAM LINE BIEAK (MSLB) INDUCED TUBE LEAK (S) CR RUPTURE (S)*
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- THE MSLB INDUCED SINGLE AND MULTIPLE (3
TUBE RUPTURE EVENTIS LIMITING
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GENERAL METHODOLOGY
- l. USE ANO-2 SIMULATOR AND " LIVE" CREWS TO j
q DETERMINE BEST ESTIMATE OPERATOR RESPONSE TIMES FOR REPRESENTATIVE 1
MSLB/SGTR SCENARIOS i
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- 2. INCORPORATE THESE RESULTS INTO ANO-2 SPECIFIC CEPAC EVALUATIONS OF VARIOUS
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MSLB/SGTR SCENARIOS
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ADEQUACY OF EOP FOR MULTIPLE g
CASUALTY EVENTS j
SIMULTANEOUS MSLB AND SGTR SCENARIOS WERE RUN E~j
. EOP GUIDANCE FOR DIAGNOSIS AND CORRECTIVE c)
ACTION WORKED WELL l7)
. PLANT WAS ON SDC WITHIN 2 HOURS
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CONSEQUENCES i
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DOSE CONSEQUENCES (CONTINUED)
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O 10CI'R100 LIMITS ARE EXCEEDED ONLY FOR SCENARIOS USING SRP ASSUMPTIONS g
REALISTIC ASSUMPTIONS ARE WELL BELOW THE 10CFR100 LIMITS l
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CEPAC RESULTS SUPPORT CONSERVATIVE HAND CALCULATIONS g
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RWT INVENTORY l3 METHODOLOGY:
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. USED ANO-2 FULL SCALE SIMULATOR AND BEST ESTIMATE (CEPAC) ANALYSIS
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SUMMARY
OF RWT INVENTORY USAGE
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RWT Usage l ANO 2 Simulator Results l
ANO-2 CEPAC Results
- Failed Tubes
% Indicated Gallons
% Indicated Gallons Level Level 1
7 33656 8.8 42460 2
N/A N/A 9.8 46964
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3 11 52888 10.6 50940 l
RESULTS:
u CONFIRMED APPLICABILITY OF NUREG 1477
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ANALYSIS TO ANO-2 1
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SAFETY ASSESSMENT
SUMMARY
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. FOR THIS LOW PROBABILITY EVENT, REALISTIC
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ASSUMPTIONS YIELD DOSE CONSEQUENCES
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CONFIRMED CONSERVATISM IN NUREG-1477 DOSE ASSESSMENTS
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3 MONITORING / PROCEDURE CONTROLS
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PROCEDURAL LEAK R. ATE LIMIT = 0.1 GPM (TECH SPEC LIMIT = 0.5 GPM) n UPON ANY CONTROL ROOM ALARM, 2
OPERATIONS AND CHEMISTRY ENTER
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ABNORMAL OPERATING PROCEDURES WITH LEAK RATE 2 0.1 GPM, PLANT SHUTDOWN IS PROCEDURALLY REQUIRED DEGRADING LEAK RATES WHERE LEAK RATE 2 0.1 GPM IS PROJECTED IN ONE HOUR, q
SHUTDOWN IS PROCEDURALLY REQUIRED
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I STABLE LEAK RATES <0.1 GPM
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PROCEDURALLY REQUIRE MANAGEMENT
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AWARENESS / ACTION FOR CONTINUED
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PLANT OPERATIONS
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- iG CG MONITORING / PROCEDURE CONTROLS El (CONTINUED) g SECONDARY RADIATION MONITORS
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WITH CONTROL ROOM READOUTS I'~0 DEDICATED SECONDARY RADIATION
[s ALARM WINDOW
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PROCEDURALLY CONTROLLED ADJUSTABLE ALARM SETPOINTS
[0 CONDENSER OFF GAS MONITOR L.
S/G BLOWDOWN MONITORS
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MAIN STEAM LINE MONITORS IIl 9
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CONTINUOUS TRENDING CAPABILITY 1._}
COMPUTER READOUTS IN CONTROL ROOM e
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DEDICATED ALARMS IN CONTROL ROOM u
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DETECTION LIMIT APPROXIMATELY 5.25 GPD (.004 GPM) g.
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MONITORING / PROCEDURE CONTROLS 7;
(CONTINUED)
OPERATOR TRAINING 7)
{J CONTINUING TRAINING l[j MULTIPLE SIZE LEAKS / RUPTURES TJ MULTIPLE EVENTS
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INSTRUMENTATION CHANGES 1
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20go CL TOP OF TUBESHEET MRPC, BOTH SG's gE
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CONCLUSIONS 0
. FORMAL EDDY CURRENT ANALYSIS GUIDELINES ARE CONSERVATIVE AND CURRENT WITH 3
INDUSTRY LEADERS
. COMPREHENSIVE EDDY CURIENT EXAMINATION AND TESTING PROGRAuM 100% REPAIR OF ALL CIRCUMFERENTIAL CRACK INDICATIONS 3
STATISTICAL PROJECTIONS, WITH CONSERVATISM APPLIED, INDICATE WITH A HIGH DEGREE OF CONFIDENCE NO FLAWS WILL BE PRESENT DURING 2R10 WHICH EXCEED REG. GUIDE 1.121 ACCEPTANCE CRITERIA
~
CONSERVATIVE ANALYSIS DEMONSTRATES i
OFFSITE CONSEQUENCES WITHIN 10CFR100 LIMITS CONSIDERING WORST CASE SCENARIO 3
. INSTRUMENTATION, PROCEDUPES, AND OPERATOR TRAINING ASSURE PROMPT AND APPROPRIATE RESPONSE TO LEAKAGE
. CONTINUED OPERATION OF ANO-2 UNTIL 2R.10 b
(SCHEDULED FOR MARCH 1994) DOES NOT REPRESENT AN UNDUE RISK TO PUBLIC HEALTH AND SAFETY 51
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