ML20090J918
| ML20090J918 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/16/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Roe J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082380335 | List:
|
| References | |
| FOIA-91-106 NUDOCS 8711200005 | |
| Download: ML20090J918 (49) | |
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e November 16, 1587 MEMORANDUM FOR:
Jack W. Rot, Division of Licensee Performance and Quality Evaluation, NRR Lawrence Shao, Director Division of Engineering and Systems Technology, NRR F R0th Steven A. Varga, Director Division of Reactor Projects - I/II, NRR FOLLOW-UP ACTIONS COPHISSION BRIEFING ON NORTH ANNA -
SUBJECT:
UNIT 1) TEAM GENERATUR TUBE RUPTURE EVENI ~
The need for fo' low-up of a number o' items were identified as a result of the staff's November 9, 1987 briefing to the Commission on the subject event.
Although a Commission final request will be following, action on the following items should be started as soon as possible.
The Lead Manager is identified for each item and schedules where appropriate.
Specifically:
_The adequacy of shift staffing on a generic basis to properly man 1.
communications system with NRC without interfering with plant operations during emergency situations.
(Roe)
Recent audits of plant Procedure Generator Packages and Emergency 2.
Onerating Procedures at several facilities have indicated deficiencies.
These deficiencies indicate that additional audits be scheduled and conducted at more facilities.
(Shao)
Complete the arranging of meetings with the licensees of those 3.
facilities identified as most susceptible to steam generator tube fatigue - type failures.
All meetings are to be conducted and completed by November 25, 1987.
(Varga)
Review adequacy of steem generator leak rate detection systems 4.
(i.e., sensitivity, criteria and administration controir for Westinghouse designed facilities.
(Shao) related Develop a program and implement generic resolution of fatigue 5.
steam generator tube failure issue, including activation of Westinghouse Regulatory Response Group.
Integrate resolution in USI A-3, A-4 and A-5.
(Shao) p_._._.-
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... November 16, 1987 Maintain cogni:ance of above activities and prepare report to the 6.
Commirision on activities and lessons learned for the event.
(Varga - scheduled to be developed).
Please provide to Leon Engle, the Lead Project Manager, your contact and This information should be proposed milestones fo* completing the above iter.s.
provided no later than November 23, 1987.
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- REDUCE FUTURE FATIGUE USAGE
- ALTERNATING STRESS REDUCTl0N
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R9C51 TUBE STABILIZATION
- HOT LEG CABLE STABILIZER
- COLD LEG SPEAR STABILIZER /SLEEYE CONNECTION i
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- REDUCE BUNDLE FLOW TO LOWER TUBE LOADS
- LOADING IMPROVEMENT, 8 - 15%
PREVENTIVE PLUGGING
- TUBES EXCEEDING LOADING CRITERIA AND HAVING NO AYB SUPPORT
- ADDITIONAL TUBES SELECTED TO IMPROVE MARGIN
- SENTINEL PLUGS UTILIZED TO PROYlDE FOR A FUTURE DATA BASE
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- TOP TIJBE SUPPORT PLATE DENTING
- S.G. THERMAL HYDRAULIC LOADING CONDITIONS
- SCREENING CRITERIA DEVELOPED BASED ON NO. ANNA EXPERIENCE RESULTS
- TYPE I AND TYPE 11 PLANTS
- HANDFUL OF TYPE I (POTENTIALLY SUSCEPTIBLE)
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- NRC INFORMED OF (Y) ACTIVITIES RECOMMENDATIONS TO ALL UTILITIES
- CONFIRM DENTING STATUS
- QUALIFY AYB POSITIONS
- REVIEW LEAK RATE MONITORING
- TECHNICAL MEETING-ON-GOING GENERIC ACTIVITIES o
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- ADDITIONAL INFORMATION DEMONSTRATES THE C6NSERVATISMS OF THE NO. ANNA CRITERIA AND MODIFICATIONS J
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h NO. ANNA S.G. MODIFICATIONS J
r F
R9C51 TUBE STABILIZATION 3
- RESTORE INTEGRITY TO R9C51 U-BEND t
DOWNCOMER FLOW RESISTANCE PLATE I
- REDUCE VIBRATION LOADS f
PREVENTIVE PLUGGING
- INCORPORATE ADDITIONAL MARG!N l
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DOWNCOMER FLOW RES! STANCE PLATE EXPERIENCE INTRODUCED IN EARLY S.G. FOR CIRCULATION CONTROL
- THERMAL HYDRAULIC STABILITY I
- M0'STURE SEPARATOR LOADING l
- MIX OF CONFIGURATIONS OPERATING PRIOR EXPERIENCE f
- CIRCULATION RATIO (CR) RANGES FROM LOW 2'S TO OVER 5
- IN-BUNDLE INSTRUMENTATION EXPERIENCE 1
_ THROUGHOUT THE CR RANGE I
NO. ANNA DESIGN SELECTION
- MAXIMlZE REDUCTibri IN YlBRATION LOADS e
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- STAY WITHIN PRIOR EXPERIENCE BASE l
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^ WkN-GENERIC CONSIDERATIONS
-INFORM OWNERS OF (W) PLANTS l
- CRITICAL INFORMATION RECOMMENDAT!ONS
-PLANT CHARACTERIZATION STUDY l
. - MEET PLANT SPECIFIC NEEDS l
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RELATIVE FLUIDELASTIC STABILITY RATIOG
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Ccenpare relative susceptibility to fluidelastic instability Relative to stability ratio (SR) s (VRM for North Anna 1 i
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LOADING EVALUATION - NORi1ALIZED STABILITY RATIO gg gm nernt una
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Evaluation based upon nominal power capa.bility parasatars a.nd plant cata where availm.ble.,
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Denting status based upon Westingbouse infomtion of known conditions.
3.
Configuration based upon Westingt.ouse records and plant data where available.
4.
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All type 3 B.G. 's have normalized. stability atios less than 0.7.
I
WESTINGil0USE PLANT 0WNER COMMUNICATIONS (Y) NOTIFICATION LETTER SEPTEMBER 1987 PLANT CHARACTERIZATION IDENTIFIED STRESSED QUANTIFICATION OF S.G. CONDITIONS
- TOP TUBE SUPPORT PLATE DENTING
- AVB POSITIONS
- REYlEW LEAKAGE MONITORING (X) TECHNICAL MENTING OCTOBER 1987 ALL (W) PLANT OWNERS INVITED DETAILED TECHNICAL SEMINAR j
VA. POWER PARTICIPATED IN PRESENTATION STRESSED UNDERSTANDING OF PHENOMENA
- RESULTS OF DENTING
- VIBRATION CONSIDERATIONS INSPECTION PARAMETERS
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- a. Su, 7U 1.0 1.0 170 B.813x109
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1 i
STRESS - STABILITY RATIO REDUCTION SELECTION i
l'
- BASED ON PROVIDING VERY LOW FUTURE USAGE I
- R9C51 RECENT ALTERNATING STRESS ASSESSMENT SUGGESTS 10% REDUCTION EXCEEDS MINIMUM REQUIRED EVALUATION OF CRACK GROWTH POTENTIAL
- STRESS LEVEL ASSOCIATED WITH ACCEPTANCE CRITERIA
- CRACK SIZE NEAR TIIAT ASSOCIATED WITH CONVENTIONAL INSPECTION METHOD DETECTION I
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i I
RESULTS:
The tube vibration below the tlweshold velocity is small.
l typical of turbulence-induced vibration.and increases very rapidly when the threshold velocity for the initiation of i
fluideiastic vibration is exceeded.
Configuration R9C51 has the lowest tlweshold velocity of mII the configurations tested.
f 4
The instability of R9C51 is very repeatable and the configuration was periodicaEy rerun to sucessfully verify the l
cons!stency of the t:sts apparatus
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