ML16138A434
| ML16138A434 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 04/02/1980 |
| From: | Siegel B Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16138A435 | List: |
| References | |
| NUDOCS 8004210328 | |
| Download: ML16138A434 (32) | |
Text
MEETING
SUMMARY
DISTRIBUTION NRC PDR (*)
LPDR (*)
ORB 4 ROG NRR RDG RSB RDG H. Denton E. Case V. Stello R. Vollmer W. Russel B. Grimes T. Carter D. Eisenhut R. Reid D. Garner M. Fairtile C. Nelson G. Vissing D. Dilanni H. Silver S. Lewis R. Hoefling L. Swartz R. Ingram P. Kreutzer OI&E (6)
R. Fraley, ACRS (16)
J. Buchanan TERA D. Ross W. Kane T. Novak S. Israel G. Mazetis P. Matthews C. Liang B. Wilson Z. Rosztoczy P. Norian B. Sheron W. Jensen R. Capra R. Woodruff P. Tam G. Holahan D. Zieman T. Spels B. Wilson
- 50-268, 50-270
-287 A. Gill 50-289, 50-302, 5 T. Harpster 50-313, 50-346 L. Phillips R. Tedesco
MEMORANDUM FOR: T. M. Novak, Chief, Reactor Systems Branch, DSS FROM:
B. L. Siegel, Reactor Systems Branch, DSS
SUBJECT:
SUMMARY
OF FEBRUARY 22, 1980 MEETING WITH THE BABCOCK AND WILCOX (B&W) OWNERS GROUP TO DISCUSS ABNORMAL TRANSIENT OPERATIONAL GUIDELINES (ATOG)
On February 22, 1980, the B&W Owner's Group and representitives of B&W met with the NRC staff in Bethesda, Maryland, to provide the staff with an update of the Owner's Group program for complying with the requirements of Section 2.1.9 of NUREG-05f8 (Analysis of Design and Off-Normal Transients). is a copy of the meeting agenda. A list of attendees is provided in Enclosure 2.
The B&W Owner's Group provided a handout of their presentation.,
which is a copy of this handout, contains the following: 1) flow chart of the program, 2) the purpose of some of the major functions, 3) the categories of transients selected for analyses, 4) representative boudding curves that identify safe and unsafe normal operation and post-transient conditions, 5) an outline of the B&W operating guidelines concept, 6) outlines of the types of immediate and followup procedural actions to be performed for the categories of accidents selected, and 7) an outline of the technical basis being developed that provides justification for the operational procedures.
During the course of the meeting, the following issues relative to the Owner's Group presentation were raised and discussed:
Consequent.14l Failures (failures due to environment): Owner's Group stated instrumentation failures and errors are being considered, however, equipment failures were not. Long-term commitment to consequential failures was noted and intthe short-term it was stated that these type failures Wuld be Included if justified based on previous experience. Consequential failures inside containment (i.e., control systems, PORV, control valves) will be included.
ATOG Study Limitations: Owner's Group stated initial effort directed at transients during power operation because It covers most of the conditions of concern. Some of the other operational modes will be covered by the ICC guidelines.
OFFiCE 0 S R A E --
SURNAMED i1 DATEN ---------
NRC Form 318A (4-79) NRCM 02040
- U.S. GOVERNMENT P..NT.NG OFFCE 1079 -
12-m37
0 T. H. Novak
-2 Quality Sontrol of ATOG: Based on Owner's Group comment that scenarios were postulated to determine if they "were. covered by the event trees developed, the staff questioned if records were being kept of all work being performed under ATOG. The Owner's Group stated that everything of importance has been included, however, not all the scenarios developed have been documented.
Application of Guidelines: Owner's Group stated that the decision as to the degree to which the plant specific procedures are adopted from the guidelines will be up to the individual utilities. This may vary from complete adoption to partial folding into existing plant procedures.
Schedule: The Owner's Group stated that they could not meet the early 1980 (March 31, 1980) completion date identified in Table B-2 of NUREG-0578.
Projectdp completion date is Mid-1980 with implementation about August 1980.
Following the presentation, a staff caucus was held during which it was agreed that the B&W Owner's Group approach to complying with the requirements of Section 2.1.9 of NUREG-0578 was acceptable. It was also decided that the Owner's Group should provide a sample package for the staff's evaluation which contains:
- 1. Events trees
- 2. Draft guidelines (including a written description of methodology and how it was determined)
- 3. Description of how Items 1 and 2 mesh into overall effort for the development of emergency operational guidelines (i.e., ICC guidelines)
The Owner's Group was requested to provide a schedule for the above package and notify the staff by February 29th.
The dates provided were April 1, 1980 for the event trees and July 1, 1980 for the guidelines and descri'tion of how this effort meshes with the overall effort.
Byron L. Siegel Reactor Systems Branch Division of Systems SAfety
Enclosures:
- 1. Agenda
- 2. List of Attendees
.~
- 3.
B&cAOGu
- Presentation OFFICEP-DSS
- RSB
. RS B-BSie el:
azetis yak DATE P 4// /80 411 1 7
1 NRC-Fo-----rm 318B (79NC04u--o----------------
o
-m--------
NRC Form 318B (4-79) NRCM 0240
- U.S. GOVISlNMENT PRNTN O-IC:
1979
-Z89-371 UNITED STATES NUCLEAR REGULATORY COMMISSION x
WASHINGTON, D. C. 20555 FEB 15 80 Docket Nos.: bO-269, 50-270, 50-287 5U-289, 50-302, 50-312, 50-313, 50-346 MEMORANDUM FOR:
W. F. Kane, Acting Chief, Standardization Branch Division of Project Management FROM:
R. A.CAPRA, B&W Project Manager Standardi'zation Branch, DPM
SUBJECT:
FORTHCOMING MEETING WITH THE ABNORMAL TRANSIENT OPERATIONAL GUIDELINES (ATOG) SUBCOMMITTEE OF THE BABCOCK & WILCOX OWNERS' GROUP TIME & DATE:
12:15 P.M., FRIDAY, FEBRUARY 22, 1980 LOCATION:
Phillips Building -
Room 422 PURPOSE:
To discuss with the B&W Owners' Group the progress made on the "ABNORMAL TRANSIENT OPERATIONAL GUIDELINES" program in support of Section 2.1.9 of NUREG-0578 PARTICIPANTS:
NRC:
T. Novak, 5. Israel, G. Mazetis, B. Wilson, B. Boger, B. Siegel, L. Phillips, R. Capra B&AO LICENSEES:
(ATOG SUBCOMMITTEE OF THE B&W OWNERS' GROUP):
Duke Power Company (Oconee 1, 2 & 3)
Metropolitan Edison Co. (T I-)
Florida Power Corporation (Crystal-iver 3)
Sacramento Municipal Utility District (Rancho Seco)
Arkansas Power & Light Company (ANO-l)
Toledo Edison Co. (Davis-Bessel)
B&W: T.
Kelly, D. Napior, et al R. A. Capra, Project [anager Standardization Branch Division of Project anagement cc:
B&v B&W Licensees
MEETING NOTICE DISTRIBUTION
- Docket Files
- NRC PDR
- LPDR Standardization Branch Reading File ORB #4 Reading NRR Reading H. Denton E. Case D. Eisenhut R. Vollmer W. Russell B. Grimes T. Carter A. Schwencer D. Ziemann T. Ippolito R. Reid
- Docket Nos: 50-269, 50-270, 50-287, V. Noonan 50-302, 50-312, 50-313, P. Check 50-346 G. Lainas G. Knighton M. Fairtile H. Silver S. Wookey D. Garner G. Vissing R. Ingram P. Kreutzer OELD - S. Lewis, D. Black, R. Hoefling OI&E (3)
OSD S. Showe, I&E (PWR)
Receptionist, Bethesda R. Fraley, ACRS (16)
TERA J. Buchanan NRC Participants W. Gammill J. Souder -
Adv. copy for R-S LPDR
ENCLOSURE 2 LIST OF MEETING ATTENDEES NRC/B&W OWNERS GROUP MEETING ON ATOG B. Wilson NRC/OLB B. Siegel NRC/RSB T. M. Novak NRC/RSB G. M. Holahan NRC/AB W. L. Jensen NRC/AB S. Israel NRC/RSB A. M. Gill NRC/RSB T. Harpster NRC L. E. Phillips NRC/AB Z. Rosztoczy NRC/AB T. J. Myers Toledo Edison J. N. Pope Duke Power Co.
R. L. Gill Duke Power Co.
S. R. Lewis Duke Power Co.
H. M. Perry Florida Power Co.
D. A. Napior B&W R. J. Finnin B&W J. J. Kelly B&W R. C. Twilley B&W
ABNORMAL TRANSIENT OPERATING GUIDELINES (ATOG)
B&W OWNERS GROUP SUBCOMMITTEE MEETING FEBRUARY 22, 1980
ATOG Objective Simplify operator problem of identifying and treating abnormal transients
Transients Selected for Guideline Preparation O Increase in heat removal by secondary system e Small steam leaks
- Excessive feedwater flow 0- Decrease in heat removal by secondary system
- Loss of feedwater o Loss of station power 0 Decrease in reactor coolant inventory
- Steam generator tube rupture e Inadequate core cooling
- Loss of coolant
Abnormal transient operating guidelines program UTILITY INPUT DATA TRANSIENT ANALYSES r,7,-,TDEFINES TIME TO KEY EVENTS.
SAFETY SE UENCE IAGRAH SAFEY SQUECE DAGRM
.CONFIRMS PARAMETER TRENDS, DRAFNZEPANTT UD D
T EPROVIDES SPECIFIC SYMPTOMS TOEPR O R
1A PNTO EVENT TREE FOR SELECTED EVENT TREE SAFETEUCI IN TO SYSTEMATICALLY DETERMINE VARIOUS BRANCHES CORRE E ATN FUO NS AD
.PLANT CONDITIONS WHICH CAN EVOLVE IDENTIFIES SYSTEM/0PER FOLLOWING A POSTULATED INITIATING RESPONSE DURING EVENT E
T TRAFT GUIDELINES DRAFT GUIDELINES ENPASN PART I PART II THOUGHTS A1.
SYETTS EXPECTED PLANT RESPONSE PROCESS AND CAUSE WW~cELS (SAO'S)
- 3.
PRECAUTIONS RDS INFORMATION FOR DETERMINING GINSOR CORRECTIVE ACTIONS FOR THE UNDLLWP CIOSOERSTANDCAN CPERATING GUIDELINES
.tESTN WALK THROUGH AT UTILITY WITH TRAINING SIMULATOR TEST GUIDELINES TO ASSURE ACCURACY OF RESULTANT.
PLANT RESPONSE FINAL TRANSIENT OPERATING GUIDELINES UTILITY WRITES PROCEDURES OPERATOR TRAINING
Event Trees Purpose Systematically determine various plant conditions which can evolve following a postulated initiating event Assumptions Initial conditions Equipment failures Operator action
Analysis
Purpose:
Realistically portray expected plant response Analyze: Design success path All single failure paths Discuss subsequent failures:
Verify LOCA paths covered in small break guidelines
Design Basis/Expected Plant Response 0 Communication between designer and operator o Supports operator action portion of guidelines O Written for operator understanding
Training Simulator
- Test various methods of approach to guidelines Verify final product Train operator
Operator Feedback 0 Detailed review of event trees o Input to guideline format O Plant walk through 0C Training
ATOG OBJECTIVES I, KEEP THE CORE COOLED -
PROVIDE ADEQUATE CORE COOLING II.
MINIMIZE RADIATION RELEASE III. PREVENT A LOCA - IF POSSIBLE IV.
PREVENT OR MINIMIZE EQUIPMENT DAMAGE V. TERMINATE TRANSIENT -
STABILIZE PLANT VI. IMPROVE THE COMMUNICATION OF INSTRUCTIONS TO THE OPERATOR TO HELP HIM PROPERLY MANAGE THE TRANSIENT
SYMPTOMS
- 1. LACK OF ADEQUATE SUBCOOLING MARGIN
- 2. LACK OF PRIMARY TO SECONDARY HEAT TRANSFER
- 3. TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER
- 4.
NORMAL
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- t IPO T REFACTOR TRIP
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~ r& CONDARY-SYSTEM -PRESSUR8E/IEf iPE-RATHRE -
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T-cold T-hot 0
Saturation Temperature of Steam.Generator Pressure ULJ POWER OPERATION T
P1U TEMPERATURE
LJ C/)
C.
NORMAL POST-TRIP CONDITIONS T E M P E R A T U R E
L, 0
Cl-LACK OF ADEOUATE SUBCOOLING MARGIN T EI TEMPE ATUR
- 0 L.
LACK OF ADEQUATE PRIMARY TO SECONDARY HEAT TRANSFER TEMPERATU RE
C/70 LUJ C-/
LUI C1 TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER (overcooling)
T E M P E R A T U R E
B&W opertingguideine concept Actions to be taken in immediate Immediate actions response to a reactor trip Follow-up actions 'Actions for treatment of lack of adequat subcooling margin, lack of primary to secondary heat transfer arid too much
___________primary to secondary heat transfer t
Long term plant Directions for appropriate follow a recovery on procedures after plant stability is achieved Expected plant A discussion, written for operator response and comprehension, of the design plant design basis response to each initiating event, potential failures and possible corrective C
actions. This section discusses the heat ctransfer from the core to the ultimate heat sink during different aspects of each transient and expins why the t
operator is taking each action. The format closely parallels Part.
REACTOR TRIP ADEQUATE CORE COOLING I. IMMEDIATE ACTIONS II. VERIFICATION OF KEY PLANT PARAMETERS AND VITAL EQUIPRENT STATUS.
A. CORRECTIVE ACTIONS (IF NECESSARY)
B. ALTERNATE ACTIONS (IF NECESSARY)
III.
IDENTIFICATION OF FOLLOWUP ACTIONS A. "NORMAL" PLANT RESPONSE - FURTHER ACTIONS (RETURn TO POWER/COOLDOWN) AT PLANT MANAGEMENTS DISCRETION B. LACK OF ADEQUATE SUBCOOLING MARGIN C. LACK OF PRIMARY TO SECONDARY HEAT TRANSFER D. TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER (OVERCOOLING)
IV. ACTIONS FOR LACK OF ADEQUATE SUBCOOLING MARGIN A. INITIAL ACTIONS B. IF INITIAL ACTIONS REGAINED SUECOOLING TREAT OTHER SYMPTOMS OR COOLDOWN/HEATUP PLANT C. IF INITIAL ACTIONS DID NOT REGAIN SUPCOOLING START HPI (IF NOT ALREADY AUTO-INITIATED)
D. IF SUBCOOLING IS REGAINED TREAT OTHER SYMPTOMS OR COOLDOWN PLANT.
E. IF SUBCOOLING IS NOT REGAINED FOLLOW ACTIONS FOR A LOCA (IFDEPRESSURIZED FAR ENOUGH) OR GO TO NEXT SECTION (IF NECESSARY)
OR COOLDOWN PLANT.
0 0
V. ACTIONS FOR TREATMENTOF LACK OF PRIMARY TO SECONDARY HEAT TRANSFER A. FEED OTSGs TO APPROPRIATE LEVEL IF NECESSARY B. IF HEAT TRANSFER IS REGAINED GO TO APPROPRIATE COOLDOWN/HEATUP PROCEDURE C. IF HEAT TRANSFER IS NOT REGAINED 1,
INITIATE HPI (IF NOT AUITO-INITIATED)
- 2.
IF OTSGs CANNOT BE FED THEN COOLDOWN
- 3.
IF OTSG LEVELS ARE CORRECT BUMP RC PUMPS D. IF HEAT TRANSFER IS REGAINED THEtl COOLDOWN WITH OTSGs E
IF HEAT TRANSFER CANNOT BE REGAINED CONTINUE HPI COOLING
VI.
ACTIONS FOR TREATMENT OF TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER A. REACTOR BUILDING TEMPERATURE/PRESSURE INCREASING
- 1. NO SLBIC ACTUATION A. ACTIONS TO STOP COOLDOWN B, COOLDOWN PLANT
- 2. SLBIC ACTUATION A. ACTIONS (STOP COOLDOWN IF SLBIC DIDN'T)
B.
COOLDOWN PLANT B. REACTCR BUILDING TEMPERATURE/PRESSURE NORMAL
- 1. INITIAL ACTIONS
- 2. NO SLBIC ACTUATION A. ACTIONS TO STOP COOLDOWN B. PLANT HEATUP/COOLDOIN AT DISCRETION OF PLANT MANAGEMENT
- 3. SLBIC ACTUATION A. ACTIONS (STOP COOLDOWN IF SLBIC DIDN'T)
B. PLANT HEATUP/COOLDOWN AT DISCPETION OF PLANT MANAGEMENT
ATOG GUIDELINES PART II SECTION 1.
FUNDAMENTALS OF REACTOR CONTROL FOR ACCIDENTS INTRODUCTION A. BASIC HEAT TRANSFER B. ABNORMAL ACCIDENT DIAGNOSIS AND MITIGATION C. POST ACCIDENT SYSTEM STABILITY DETERMINATION D. FOLLOWUP ACTIONS APPENDIX A - SUPERHEAT, SATURATION, SUBCOOLING APPENDIX B - NATURAL CIRCULATION SECTION 2, GUIDELINES FOR SELECTED ACCIDENTS WITH 11ULTIPLE EQUIPM1ENT FAILURES A. EXCESSIVE iMAIN FEEDWATER B. SLB C. STR D. LOSS OF A/C POWER E. LOSS OF MAIN FEEDWATER F. SBLOCA "FOLDOUT" SUMNARIES I. - BASIC HEAT TRANSFER RELATIONSHIPS
- DIAGNOSIS AND MITIGATION II. -
EXCESSIVE FEEDWATER LOMFW
-STR LOSS OF A/C POWER SLB
PART II Section 1. FUNDAMENTALS OF REACTOR CONTROL FOR ACCIDENTS INTRODUCTION A. Basic Heat Transfer Steam Generator Pressure Control
- Steam Generator Inventory Control
- Reactor Coolant Inventory Control
- Reactor'6olant Pressure Control B. Abnormal Accident Diagnosis and Mitigation Immediate actions (2 to 3 minutes)
- Quick followup actions (Equipment Status)
- Abnormal? (ATOG or not) a)
P-T plot description b) Pre-trip discussion c)
Normal post trip transient d) Abnormal post tip transient
- Subcooling rule a) with over-heating b) with over-cooling
- Backup methods of cooling a)
HPI b)
LPI c) Condensate Pump d) Auxiliary Feedwater Pump
- Cause Wheels
- Preferred method of equipment operation a) RCP's b) HPI Throttling c)
Termination of MFW C. Post Accident System Stability Determination Checklist for defining stability
- Measure of successful termination of transient
D. Followup Actions Decide long term plant disposition
- Transfer to appropriate procedure Appendix A - Superheat, Saturation, Subcooling Appendix B - Natural Circulation Section 2. GUIDELINES FOR SELECTED ACCIDENTS WITH MULTIPLE EQUIPMENT FAILURES A. Excessive Main Feedwater One page summary
- 1. General Transient Description Operator Action Summary
- a. Identify the accident
- b. Corrective action
- c. Schematic summary of operator action
- 2. Excessive Main Feedwater with Other Plant Failures Reactor Pressure Reactor Inventory Steam Pressure Steam Generator Inventory