ML16245A447
| ML16245A447 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 08/24/1979 |
| From: | Capra R NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| To: | NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| References | |
| NUDOCS 7910090536 | |
| Download: ML16245A447 (41) | |
Text
ow Dpt RENos UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 AUG 24 1979 k>
Docket Nos.:
50-269, 50-270, 50-287 50-289, 50-302, 50-312 50-313, 50-346 FACILITIES:
Oconee Nuclear Station, Unit Nos. 1, 2, & 3 Three Mile Island Nuclear Station, Unit No. 1 Crystal River Nuclear Generating Station, Unit No.,3 Rancho Seco Nuclear Generating Station Arkansas Nuclear One, Unit No. 1 Davis-Besse Nuclear Power Station, Unit No. 1 LICENSEES:
Duke Power Company Florida Power Corporation Sacramento Municipal Utility District Arkansas Power & Light Company Toledo Edison Company Metropolitan Edison Company
SUBJECT:
SUMMARY
OF MEETING HELD ON AUGUST 9, 1979, WITH THE BABCOCK & WILCOX (B&W)
OWNERS' GROUP TO DISCUSS LONG TERM GENERIC REQUIREMENTS FOR B&W OPERATING PLANTS On August 9, 1979, members of the NRC staff met with the B&W Owners' Group (TMI-2 Follow-up Subcommittee) and representatives of the B&W Company, in Bethesda, Maryland to discuss various long-term generic requirements applicable to the B&W operating plants. Enclosure 1 is a copy of the meeting agenda. A list of attendees is provided as Enclosure 2.
BACKGR OUND During meetings held on July 18 and 19, 1979, between the NRC staff, the B&W Owners' Group, and the B&W Company, the Owners' Group committed to meet with the staff at a future date to discuss the following topics: (1) proposed outline for conducting an auxiliary feedwater/emergency feedwater (AFW/EFW) system reliability study, (2) proposed outline for providing the analyses, emergency procedure guidelines, and training needed to assure that the reactor operator can recognize and respond to conditions of inadequate core cooling. This meeting was arranged,.at the request of the Owners' Group, to discuss these topics.
DISCUSSION Agenda Item 1:
FUNCTIONING OF THE B&W OWNEFS' GROUP During the July 19, 1979 meeting between the staff and the Owners' Group, the &-oto Chairman of the TMI-2 Follow-up Subcommittee (the Subcommittee) discussed the 910090 AUG 2 4 1979 membership, scope, objectives, and organization of the Subcommittee. It was agreed upon at that time, that correspondence from the NRC requiring the expenditure of funds would not be sent directly to the Chairman of the Subcommittee but rather would be addressed to the individual member licensees. The Director, Bulletins &
Orders Task Force (Mr. D. Ross) was not at the July 19, 1979 meeting. Mr. Ross stated that in order to ensure timely resolution of all B&W generic items, it would be in the best interest of the staff and the individual members of the Owners' Group if the NFC could deal directly with the Chairman of the Subcommittee on all correspondence requiring action by the individual licensees. It was pointed out this was the procedure established by the other owners' groups (General Electric, Combustion Engineering, and Westinghouse). The Acting Chairman of the Subcommittee (Mr. R. Gill - Duke Power Company) pointed out the Owners' Group charter does not establish the Subcommittee as a legal entity and therefore it can assume no financial or legal responsibility for its members and as such all contractual matters and program funding are controlled by each individual member company. Since the members of the Subcommittee could not make commitments for their companies and since the Chairman of the Subcommittee could not speak or act for all its members, Mr. Ross expressed concern over the ability of the staff and the Subcommittee to reach timely resolution on outstanding generic issues.
Mr. Ross agreed to continue working with the Subcommittee, in the manner in which the Owners' Group's charter is written; however, he pointed out that if negative experience resulted in dealing with the Subcommittee in this manner, he would direct his staff to stop interacting with the Subcommittee and would communicate directly with individual licensees.
Agenda Item 2:
PROPOSED AFW/EFW SYSTEM RELIABILITY STUDY As part of the long-term requirements of the Commission Orders issued to each operating B&W licensee in May 1979, each of the B&W operating plant licensees is committed to continued review and upgrade of its AFW/EFW system. In order for each licensee to assess which areas of its AFW/EFW system need improvement, the staff directed that each licensee perform a study of the AFW/EFW system reliability.
This study should be of similar nature to that done by the NRC staff on each of the Westinghouse and Combustion Engineering operating plants. The Subcommittee Chairman stated that three of its member utilities had not yet contracted B&W to perform the study; however, ahy contractor picked to perform the study would utilize the same objective and scope as the proposed outline which B&W would present at this meeting. The B&W presentation covered two major areas:
(1) program description and (2) schedule for completion.
The approach taken by B&W was to include the same general methodology (fault tree techniques) as used by the NRC staff; however, the level of detail would be much more extensive.
The proposed program description is contained in Enclosures 3 through 14 of this summary. The program scope and description was generally acceptable to the staff; however, as shown in Enclosure 13, the study, as proposed, would take almost seven months to complete. The staff pointed out that this was unacceptable since the terminology used in the Commission Orders to describe the implementation of the long-term items was "...as promptly as practicable...." The staff believed that an acceptable reliability study could be completed on a lead-plant (chosen by the Owners' Group) by mid-September 1979 and that the remaining plants could be completed by mid-October 1979.
~41 Following detailed discussions, the NRC staff and the Subcommittee agreed on the following commitments:
(1) The level of detail of the study would be narrowed such that it could be completed in a time frame which the NRC staff considered as promptly as practicable.
(2) All licensees would contract B&W to perform the study with the possible exception of Toledo Edison Company (TECO) who had previously contracted with MPR Associates to do its study.
(3) By August 17, 1979, B&W would send a letter to NRC outlining its revised program description. Each licensee, in turn, would send a letter committing to the program and schedule outlined in the B&W letter.
If TECO elects not to use B&W for its study, it will send a separate letter describing its program and schedule.
(4) The Owners' Group will pick a lead-plant and provide the draft results of its study to the NRC staff by September 17,.1979. The staff agreed to meet with the Owners' Group during the week of August 27, 1979 to review the status of the lead-plant study.
(5) The draft report will be provided to the staff for review on the remaining plants by October 22, 1979.
(6) The final report will be submitted to the NRC by December 3, 1979.
Agenda Item 3: ABNORMAL TRANSIENT EVALUATION During a meeting with the Owners' Group on July 18, 1979, the NRC staff informed the Subcommittee that in addition to the evaluation of small break loss-of-coolant analysis previously required by the staff two more tasks should be undertaken:
(1) an assessment of the symptoms of inadequate core cooling and (2) an evaluation of accidents and transients beyond current design analyses. In both cases, it was emphasized that focus should be placed on the information needed for operator training and information needed for the preparation of improved emergency procedures.
The Owners' Group agreed at that time to meet with the staff at a future date to discuss its progress on these two items. These two items are addressed in recommen dation 2.1.9 of NUREG-0578, "TMI-2 LESSONS LEARNED TASK FORCE STATUS REPORT AND SHORT-TERM RECOMMENDATICNS." B&W presented an outline, on behalf of the Owners' Group, which it stated would be responsive to these areas.
The objective of B&W's program is to develop operator guidelines for a spectrum of abnormal transients. These guidelines may then be used by each licensee as a basis for developing detailed emergency procedures. The B&W operating guidelines will be divided into two parts - procedural and technical basis for the procedure.
The procedural part will encompass: (1) method by which the operator can recognize the symptoms of a transient using available alarms and indications, (2) immediate
actions which must be taken upon recognizing the existing transient, (3) precautions and limits each operator must observe, and (4) specific follow-up actions the operator must take to place the plant in a safe condition. The technical basis portion of each guideline will include: (1) a description of the cases considered and the operational strategy for each event, operational objectives, and plant equipment and features used, (2) a description of the expected plant response, and (3) references to equipment performance assumptions and supporting system analyses.
In order to develop these guidelines, B&W will use an event tree approach and methodology. For each transient, once event trees are defined and prepared, realistic analyses to confirm expected plant behavior will be developed. Several factors will be incorporated into the guidelines prior to being issued by B&W:
(1) previous transient experience on operating plants, (2) confirmation of installed equipment and equipment characteristics for each plant, (3) walk throughs with plant operating staffs, and (4) incorporation of the operating staffs' comments.
In order to be responsive to recommendation 2.1.9 of NUREG-0578, the first set of guidelines will deal with inadequate core cooling. The goals of this item will be to: (1) describe the symptoms by which an operator can recognize inadequate core cooling with existing instrumentation, (2) develop guidelines for operator action to recover from this situation, and (3) identify any additional instrumen tation which may be required to indicate inadequate core cooling. Items (1) and (2) should be completed by October 31, 1979 and item (3) should be completed by January 31, 1980. In order to proceed with this program, B&W requested clarification of their definition of inadequate core cooling; namely, "...when the RV (reactor vessel) water level falls below the top of the core with RCPs off and is followed by an increasing fuel rod clad temperature." The staff pointed out that NUREG-0578 also included examples of inadequate core cooling caused by low reactor coolant system inventory with and withoutforced flow (RCPs operating/RCPs tripped).
Subsequent to this meeting, on August 14, 1979, a phone conversation was held between Mr. Z. Rosztoczy (NRC) and Mr. E. Kane (B&W) to more clearly define the staff's position on the B&W program for inadequate core cooling. The staff desires that analyses be done for three specific conditions where inadequate core cooling can occur:
(1)'loss of inventory in the reactor coolant system (RCS) with reactor coolant pumps (RCPs) operating, (2) loss of inventory in the RCS with RCPs tripped, and (3) transients in which departure from nucleate boiling (DNB) occurs.
Information obtained from these analyses may then be used to: (1) identify response of available instrumentation, (2) prescribe limiting values for instrumentation readout, (3) develop criteria for successful recovery, (4) develop operator action for recovery, and (5) develop suggested changes to provide improved indication of inadequate core cooling. These guidelines should be developed for all modes of operation, i.e., power operation, hot shutdown, refueling, etc.
In addition to providing guidelines for inadequate core cooling, B&W will utilize the same methodology for developing guidelines for other transients and accidents on a schedule that is compatible with that shown in NUREG-0578.
AUG 2 4 1979 The transients presently selected by B&W for guideline preparation include:
(1) small steam leaks, (2) excessive feedwater flow, (3) loss of feedwater, (4) loss of station power, (5) steam generator tube rupture, (6) inadequate core cooling, and (7) loss of coolant accident. The material used by B&W during this portion of the presentation is included as Enclosures 14 through 28 of this summary.
Agenda Item 4:
REVIEW OF STATUS OF LONG-TERM GENERIC REQUIREMENTS FOR B&W PLANTS Due to shortage of time, this item was not discussed at this meeting. However, on August 20, 1979, a letter was sent from Mr. D. Ross to all B&W operating plants (except TMI-1 and TMI-2) identifying all of the generic long-term requirements associated with the Commission Orders. This letter provides a status summary and a schedule for NRC and licensee action on each item.
CONCLUSIONS AND ACTION TAKEN SUBSEQUENT TO THIS MEETING Agenda Item 1:
On August 20, 1979, a letter was sent to each licensee from Mr. D. Ross in which he asked each licensee to consider modifying the TMI-2 Follow-up Subcommittee's scope of authority, within the Owners' Group, such that the member ship of that Subcommittee would include individuals authorized to make commitments on behalf of their utilities, and ultimately help obtain prompt resolution of generic issues.
Agenda Item 2:
On August 17, 1979, B&W forwarded a proposed schedule for completing the AFW/EFW reliability study. B&W desires to arrange a meeting on August 30, 1979 to discuss its progress on the lead-plant for the study (Rancho Seco).
Agenda Item 3:
B&W has agreed to modify its program for developing operator guidelines for inadequate core cooling, such that it will incorporate the' staff's position. However, due to the expanded scope, it may not be able to complete this work by October 31, 1979. Further discussions between B&W and the staff are necessary to resolve scheduling difficulties.
Agenda Item 4:
On August 20, 1979, a letter was sent to B&W licensees identifying the long-term generic issues related to the Commission Orders of May 1979.
This letter also provided a summary and schedule for NRC and licensee action for each item.
R. A. Capra, B&W Project Manager Bulletins & Orders Task Force Office of Nuclear Reactor Regulation
Enclosures:
- 1. Meeting Agenda
- 2.
List of Attendees 3 B&W Presentation Material
ENCLOSURE 1 AGENDA FOR AUGUST 9, 1979 B&W OWNERS' GROUP MEETING 1.- Functioning of B&W Owner's Group (D. Ross)
A. authority B. responsibility C. method of communication between owners' group and staff
- 2. Proposed AFW/EFW system reliability study (Owners' Group & B&W)
A. outline of program for the development of operator guidelines B. event tree methodology C. determination of supporting analyses D. schedule
- 4. Review of status of long-term generic requirements for B&W plants (NRC staff)
A. Long-term Order requirements:
(1) failure mode and effects analysis for the ICS (S. Israel)
(2) upgrade of anticipatory reactor trip to safety-grade (S. Israel)
(3) continued operator training and drilling to assure a high state of preparedness (S. Israel)
B. Long-term requirements discussed in the staff's evaluation of licensees' compliance with Orders:
(1) analyses for LOFW and other anticipated transients - NUREG-0560, Section 8.4.1 (W. Jensen)
(2) analysis for small break LOCA - NUREG-0560, Section 8.4.2 (W. Jensen)
(3) analysis for lift frequency and mechanical reliability of PORV and safety valves - NUREG-0560, Section 8.4.6 (S. Israel)
(4) pressure vessel integrity (S. Israel)
(1) B&W Thermal-Mechanical Report (ii) revised operating curve for accident conditions C. Additional items: (S. Israel)
(1) core thermocouples (extended range and emergency power supplies)
(2) demonstration of local manual operability of automatic steam dump valves (3) evaluation of SLBIC system for steam line break
-(4) evaluation of overfeeding steam generators
- D. Lessons learned recommendations to be implemented by B&O: (references refer to page numbers in NUREG-0578)(NRC staff)
(1) emergency power supply for pressurizer heaters, level indication, PORV and block valves (A-1 (2) performance testing of PORV and safety valves (A-6)
(3) direct indication for PORV and safety valves (A-9)
(4) instrumentation for inadequate core cooling (A-11)
(5) automatic initiation of AFW/EFW (A-30)
(6) AFW/EFW flow indication to steam generators (A-32)
(7) analyses of design and off-normal transients and accidents (A-42)(partially covered in item #3 above)
(8) shift and relief turnover procedures (A-52) discussion of these items if time permits
ENCLOSURE 2 LIST OF ATTENDEES Duke Power Company R. L. Gill (Licensing)
Florida Power Corporation R. M. Bright (Nuclear Support Specialist)
Sacramento Municipal R. A. Dieterich (Senior Nuclear Engineer)
Utility District Arkansas Power & Light T.
Kilgone (Manager, Availability Engineering)
Company D. G. Mardis (Licensing Engineer)
D. H. Williams (Nuclear Operations Engineer)
Toledo Edison Company J. K. Wood (Associate Engineer)
Consumers Power Company R. M. Hamm (Midland Nuclear Safety Task Force)
Shawback Engineer)
Babcock & Wilcox Company B. J. Short (Project Manager)
E. A. Womack (Manager, Plant Design)
R. B. Davis (Project Manager)
R. C. Twilley, Jr. (Plant Performance Services Engine@ring)
E. R. Kane (Manager Operating Plant Licensing)
R. E. Ham (Product Line Manager, Engineering Services)
NRC D. F. Ross, Jr. (Director, Bulletins & Orders (B&O) Task Force)
T. M. Novack (Deputy Director, B&O Task Force)
C. J. Heltemes (Group Leader-Proj. Mgt., B&O Task Force)
S.
Israel (Group Leader-Systems, B&O Task Force)
P. R. Matthews (Section Leader-Systems, B&O Task Force)
M. A. Cunningham (Probabilistic Analysis)
M. E. Mulkey (NRC Staff Counsel)
D. L. Davis (NRC Staff Counsel) 4W. L. Jensen (Analysis Group, B&O Task Force)
P. S. Tam (ACRS)
J. G. Stampelos (ACRS)
J. A. Olshinsky (Lessons Learned Task Force)
G. M. Holahan (Lessons Learned Task Force)
R. A. Capra (B&W Project Manager, B&O Task Force)
R. W. Reid (Chief, Operating Reactors Branch #4)
ENCLOSURE 3 AUXILIARY FEEDWATER RELIABILITY STUDY AGENDA INTRODUCTION E. R. KANE PROGRAM DESCRIPTION W. W. WEAVER SCHEDULE AND
SUMMARY
E. R. KANE
ENCLOSURE 4 OBJECTIVES
- 1. PRESENT GENERAL APPROACH TO RELIABILITY STUDY
- 2. OBTAIN CLARIFICATION OF ASSUMPTIONS
- 3. IDENTIFY SCHEDULE
ENCLOURE 5 GROUND RULES PERFORM AUXILIARY FEEDWATER RELIABILITY ANALYSIS USING FAULT TREE TECHNIQUES GIVING SYSTEM UNAVAILABILITY CONDITIONED ON:
- MFW
- AC MISSION SUCCESS WILL BE DEFINED AS CHANGING STATE OF.
AUXILIARY FEEDWATER SYSTEM ON DEMAND. AUXILIARY FEED WATER SYSTEMS ANALYZED AS OF 8/1/79.
ENCLOSURE 6 ANALYSIS WILL INCLUDE HARDWARE FAILURES MAINTENANCE AND TEST CONTRIBUTIONS INTERFACING SYSTEM FAILURES
.OPERATOR ACTIONS AND ERRORS EXCLUDE FIRE FLOOD SEISMIC HIGH ENERGY LINE RUPTURES IN PWR SECONDARY SYSTEMS WATER HAMMER RUPTURE OF PIPING, VALVES, TANKS IN AFW SYSTEM
Insufficient Auxiliary Feedwater Flow m
14 Suction Pump Discharge Suction &
Suction 6 Pump &
Failures Failures Failures Pump Discharge Discharge 0
ENCLOSURE 8 FAULT TREE QUANTIFICATION FTAP AND KITT SAMPLE MAY BE USED.
FTAP MORE VERSATILE MORE EFFICIENT THAN PREP.
ENCLOSURE 9 CLARIFICATIONS NEEDED
- MFW POWER t, STEAM t
- LOOP -
GRID 4, DIESEL GENERATORS t, STEAM t
ENCLOSURE 10 REFERRING TO TABLE 1 Page 20 I.- COMPONENT (HARDWARE) FAILURE DATA A. Valves i
- Control Circuit -
Valve operator only? A 5.5 x 10-6/hr?
Test consists of opening and closing valve?
B. Pumps
- Control Circuit Electric Pump A
? Quarterly and monthly tests give inconsistent failure rates
- Control Circuit Turbine Pumps A -
?
C. Actuation instrumentation X -
? per train Q-? for logic 1 out of 2 Page 21 II.
TEST AND MAINTENANCE OUTAGE CONTRIBUTORS
(# hrs/test)(# tests/yr) test
- hrs/yrs
- hrs/yr c
calendar or operating time
- tests/yr
= generic or specific; generic 7
Q diesel due to test -
? Why are diesels unavailable during test?
Instrumentation test frequency -
?
Can take credit for placing trains in logic in tripped position while tests are being performed?
a
.22(# hrs/maintenance act) maint.
720 Is PM while unit is down considered in frequency of maintenance acts?
Page 22 III.
HUMAN ACTS AND ERRORS A. Clarify XE No. of valves in population at choice auxiliary feedwater system valves only?
Similar as far as MOV or manual?
Location factors?
Functional factors?
B. More than one valve is affected (coupled errors) - 1 x 10-4 Identify requirements for choosing coupled valves. (Any additional factors than those listed under category A. above?)
C. Miscalibration of Sensors/Electrical Relays Identical equi ment only?
- A from 1 x 10- to 3 x 10- 3 due to checking? Redundant people performing initial operation?
What about both of the above, A
?
Page 23 IV.
ACTS AND ERRORS OF A POST-ACCIDENT NATURE A.
Do operator failure rates consider that operator has unmis takeable indication; indication requiring some thinking; conflicting indication requiring more thinking; no indication?
Indication probabilities used if any.,
B.
Operator failure rates during stress - Anything more specific than listed in WASH-1400, Table III 6-1?
AUXILIARY FEEDWATER SYSTEM RELIABILITY TRANSIENT EVENTS LMFW LMFW/LOOP LMFW/LOSS OF ALL AC PLANT/I UNITS LOW MED HIGH LOW MED HIGH LOW MED HIGH t-
(./,w
/
//4 P7rO.r 4 eI tA 71 4 ~r Low Low~
liei'h Hji Lowi Mcd IcjIr
& i.F.
c I
I C
I I_
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le
_ I I
I Il 0
Ij 71 0I I
aI I-91_
-1.1
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ZVf~dtr ejs~rc
SCHEDULE FOR AFW RELIABILITY ANALYSIS 1-79 9-1-79 10-1-79 11-1-79 12-1-79 1 1-80 2-1-80 3-1-80
- 1. PHASE 1, OBTAIN AFW DESIGN INFORMATION
- 2.
PHASE 2, PREPARE FAULT TREES AND PERFORM ANALYSES I. PHASE 3, PREPARE AND REVIEW REPORT ISSUE REPORT TO NRC.
2-22-80 e.
ENCLOSURE 14 ABNORMAL TRANSIENT OPERATIONAL GUIDELINES AGENDA INTRODUCTION E. R. KANE PROGRAM DESCRIPTION E. A. WOMACK
- 1.
GENERAL APPROACH
- 2. GUIDELINE STRUCTURE
- 3. TRANSIENTS TO BE EVALUATED
- 4. SCHEDULES EVENT TREE METHODOLOGY J. J. KELLY
0 ENCLOSURE 15 OBJECTIVES
- 1. PRESENT GUIDELINE STRUCTURE
- 2. PRESENT TRANSIENTS TO BE EVALUATED
- 3.
PRESENT SCHEDULE
- 4. PRESENT EVENT TREE APPROACH AND METHODOLOGY
ENCLOSURE 16 LESSONS LEARNED TASK FORCE RECOMMENDATION PROVIDE THE ANALYSIS, EMERGENCY PROCEDURES, AND TRAINING TO SUBSTANTIALLY IMPROVE OPERATOR PERFORMANCE DURING A SMALL BREAK LOSS-OF-COOLANT ACCIDENT.
PROVIDE THE. ANALYSIS, EMERGENCY PROCEDURES, AND TRAINING NEEDED TO ASSURE THAT THE REACTOR OPERATOR CAN RECOGNIZE AND RESPOND TO CONDITIONS OF INADEQUATE CORE COOLING.
PROVIDE THE ANALYSIS, EMERGENCY PROCEDURES, AND TRAINING TO SUBSTANTIALLY IMPROVE OPERATOR PERFORMANCE DURING TRANSIENTS AND ACCIDENTS, INCLUDING EVENTS THAT ARE CAUSED OR WORSENED BY INAPPROPRIATE OPERATOR ACTIONS.
NUREG 0578 PARAGRAPH 2.1.9 cd
L iLULURL 1/
.Abnormal traInsient operation.guideme DE F INE EVENT TRANSIENT EXPERIENCE CONFIRM INSTALLEDRELSI EURMN AD IIT SN YSE BTO AV OR
.0.rNIO EQUIPMENT WxrE VI H PLA TEC RECMEDTSSO ?~TR ACHARACTERISTICS P ANT LIM I NTEAUTO POTENTIAL MODIFICATIS D.
- SU IDINE PREPARE PLAFT C*
.GUDEINE INIRTIATNG EVENTL O IFCTIN PREPAREPLN REALIS TI LEFITYEREUR)ET NDLMT IRIIA P ESCRITION OF GIEIE PREPRE 1RAF
ENCLOSURE 18 B&W OPERATING GUIDELINE CONCEPT PROCEDURAL OUTLINE AND SYSTEM BEHAVIOR BASIS A SINGLE, REVISION-CONTROLLED DOCUMENT.
o GUIDELINES KEYED TO EVENT CATEGORIES.
I INITIAL RESPONSES TO BE EVENT -
INDEPENDENTS 8 EVENT RECOGNITION AND DIAGNOSIS KEYED TO A FEW FUNDAMENTAL INDICATIONS.
B & W operating guideline concept 1.0 SYMPTOMS EVENT RECOGNITION SIGNALS FROM AVAILABLE ALARMS AND INSTRUMENTATION
=
2.0 IMMEDIATE ACTIONS ACTIONS TO BE TAKEN IN IMMEDIATE RESPONSE TO THE Cm SYMPTOMS 3.0 PRECAUTIONS LIMITS TO BE OBSERVED IN THIS EVENT C) 4.0 FOLLOW-UP ACTIONS SPECIFIC ACTIONS TO ACCOMPLISH SAFE RECOVERY 5.0 BASES
- ESCRIPTION OF THE CASES CONSIDEREO AND THE OPERATIONAL STRATEGY FOR EACH (EVENT TREES). DESCRIPTION OF THE OPERATIONAL OBJECTIVES AND PLANT FEATURES USED.
6.0 PLANT RESPONSE DESCRIPTION OF THE PLANT BEHAVIOR EXPECTED DURING THIS EVENT.
7.0 REFERENCES
REFERENCE TO THE ENGINEERING DESIGN BASIS ESSENTIAL EQUIPMENT PERFORMANCE ASSUMPTIONS SYSTEM ANALYSES
ENCLOSURE 20 Operating guideline Documentation structure For each event GENERIC PLANT DATA ESSENTIAL
. EVENT TREE EQUIPMENT PERFORMANCE CALCULATION A.SSUMPT IONS FILES ENGINEERING ANALYSES PLANT BEHAVIOR BASES PROCEDURAL OUTLINE OPERATING GUIDELINE
ENCLOSURE 21 TRANSIENTS SELECTED FOR GUIDELINE PREPARATION t INCREASE IN HEAT REMOVAL BY SECONDARY SYSTEM SMALL STEAM LEAKS EXCESSIVE FEEDWATER FLOW I DECREASE IN HEAT REMOVAL*BY SECONDARY SYSTEM Loss OF FEEDWATER Loss OF STATION POWER I DECREASE IN REACTOR COOLANT INVENTORY STEAM GENERATOR TUBE RUPTURE INADEQUATE CORE COOLING Loss OF COOLANT
ENCLOSURE 22 ABNORMAL TRANSIENT OPERATING GUIDELINES SCHEDULE Aug.
Sept.
-Oct.
Nov.
Dec.
Jan.
Feb.
Mar.
Guidelines for Inadequate Core Cooling Prepare Event Trees and Define Analysis Complete Confirmatory Analysis Prepare Operating Guidelines
ENCLOSURE 23 ABRIDGEO EVENT TREE LOSS 0 via
)OR C
U:%lt Ftl:1101T Re TWER SG lvI4TCRl ST!"I P olssvolliq sr Fw1v(p Ito*
$14pfo4s 4twom TRIP Loss OF CAUSES OF.
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- 2)
CAUSES V4101.1OE
'[ACTIVITY COMIN at I
[a 1011114 TRIP "us" "ISSURMA it 11" MAY 14421.
RCP SEAL Its Its Ito IUAILIART IIIIIIMO 40 PUN 1110 AFIF FIDIF ATI IIIACEOUAII CWTROLL 0 (ICESSIVE co Me.
I I fAw Pat(*
- 2) CAUSES F-vP ELM r EXCESS
- mosm, A
C CISS ouvp EFFECT nN a.,
IS SICONOART SIDE p
1:11"luallo YES No STIPIOUS
- 2) CAUSES EVENT F
NSUIR P
lifft ps ISFAS ACTUATION C=
(No POINT it 90
[:::3-- 41! 'INER SF EVENT IRS[
let III?
117111,18A.,
I:Flll G 'a SF "101 INITIATED Nor SNOn NPI FI.C.,
lCONTROtuo I (ICESSI'l JINAOCOUATE I
- 1) SIVIFTONS
0 0
ENCLOSURE 24 GROUNDRULES FOR EVENT TREES & ANALYSES OBJECTIVES:
-REALISTIC FORECASTING OF EVENT STRUCTURED TO PRODUCE GUIDELINES o
- 1.
INITIAL CONDITIONS PRIOR OPERATION AT STEADY POWER
- 2.
FAILURES INITIATING EVENT (+) CONSEQUENTIAL ACTIVE FAILURES OPERATOR ERRORS (+) CONSEQUENTIAL ACTIVE FAILURES DEFINITIONS:
CONSEQUENTIAL FAILURE IS A FAILURE OF ANY ACTIVE FLUID SYSTEM COMPONENT CHALLENGED BY THE EVENT.
- 3.
OPERATOR AcTION CORRECT ACTION NO ACTION INCORRECT ACTION
- TIME DELAY = TIME TO REACT
- 4.
END CONDITION O-T OR COLD SHTDOWN
ENCLOSURE 25
-SYSIP rct-i 7
0! 7 cs'
- NUH1
~'/A9~.
~VU6
- .SY 7~S/~
7Ef7ihV
ENCLOSURE 26 INADEQUATE CORE COOLING I NUREG-0578 Provide the analysis, emergency procedures, and training needed to assure that the reactor operator can recognize and respond to conditions of inadequate core cooling.
t B&W GOALS (BASED UPON TMI-2 EXPERIENCE AND ANALYSIS)
Describe symptoms for operator to recognize inadequate core cooling with existing instrumentation.
Develope guidelines for operator action to recover.
Identify any additional instrumentation to indicate inadequate core cooling.
6 OUTPUT PRODUCT Operating guidelines to prescribe instrumentation limits and operator action to recover from a condition of inadequate core cooling -
October 31, 1979.
Suggested changes to provide improved indication of inadequate core cooling -
January 31, 1980.
LiLU2URE 27 RECOGNITION AND RECOVERY
-9 DEFINE INADEQUATE CORE COOLING Begins wlhnt RV water level falls below top of the core with RC Pumps off.
Is followed by an increasing fuel rod clad temperature.
I IDENTIFY RESPONSE OF AVAILABLE INSTRUMENTATION
-,Increasing fuel rod clad temperature detected by
- 1) Incore Thermocouples.
- 2)
Hot Leg RTD's.
I PRESCRIBE LIMITING VALUES FOR INSTRUMENTATION READOUT Maximum allowable temperatures.
Correlated to need for operator action.
4 DEFINE OPERATOR ACTION FOR RECOVERY More HPI flow.
Start RC Pumps.
OTSG depressurization.
I. DEFINE CRITERIA FOR SUCCESSFUL RECOVERY Core heat removal.
RC pressure control.
RC inventory control.
based upon available instrumentation
BABCOCK & WILCOX OPERATING PLANTS Mr. William 0. Parker Jr.
Vice President -
Steam Production Duke Power Company P.O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company Little Rock, Arkansas 72203 Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District 6201 S Street P.O. Boxl5830 Sacramento, California 95813 Mr. Lowell E. Roe' Vice President, Facilities Development Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Mr. W. P. Stewart Manager, Nuclear Operations Florida Power Corporation Crystal River Nuclear Plant P.O. Box 1240 Crystal River, Florida 32629 Mr. R. C. Arnold Senior Vice President Metropolitan Edison Company 260 Cherry Hill Road Parsippany, New Jersey 07054 Mr.
James H. Taylor Manager, Licensing Babcock & Wilcox Company Power Generation Group P.O. Box 1260 Lynchburg, Virginia 24505
Duke Power Company Mr. William L. Porter Mr. Robert B& Borsum Duke Power Company Post Office Box 2178 Bbok&Wlo Nuclear Power Generation Division 422 South Church Street Suite 420, 7735 Old Georoetown Road Charlotte,, North Carolina 28242 Bethesda,, Maryland 200i4 J. Michael McGarry, III, Esquire DeBevoise & Liberman NagerrtS 700 Shoreham Building NUS Corrio 806 15th Street, N.W.lawtr lrd 31 806 15t Stree, N.W.2536 Countryside Boulevr Washington, D. C.
20005 Office of Intergovernmental Relations Honoable~
116 West Jones Street Honorable Janes H. Phinney County Supervisor of Oconee County Raleigh, North Carolina 27603
-Walhalla, South Carolina 29621 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2
- Arlington, Virginia 20460 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street, N.E.
- Atlanta, Georgia 30308 U. S. Nuclear Regulatory Commission Region II Office of Inspection and Enforcement ATTN:
Mr. Francis Jape P. 0. Box 85 SenEca, South Carolina 29678
Arkansas Power & Light Company Philip. Lyn, sq.Director, Technical Assessment Phillip K. Lyon, Esq.
House, Holms & Jewell 1550 Tower Building Office of Radiation Programs Little Rock, Arkansas 72201 (AW-459)
U. S. Environmental Protection Agelc:
Mr. David C. Trimble Crystal Mail #2 Manager, Licensing Arlington, Virginia 20460 Arkansas Power & Light Company P. 0. Box 551 U. S. Environmental Protection Agenc:
Little Rock, Arkansas 72203 Region VI Office ATTN: EIS COORDINATOR Mr. James P. O'Hanlon 1201 Elm Street General Manager First International Building Arkansas Nuclear One Dallas, Texas 75270 P. 0. Box 608 RusselIville, Arkansas 72801 Mr. William Johnson Director, Bureau of Environmental U. S. Nuclear Regulatory Commission Health Services P. 0. Box 2090 4815 West Markham Street Russellville, Arkansas 72801 Little Rock, Arkansas
-72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland
- 20014, Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse RusseDlville, Arkansas 72801
Page 2 of 2 Sacramento Municipal Utility District Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission
- Washington, D.C.
20555 Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Richard D. Castro 2231 K Street Sacramento, California 95814 Mr. Gary Hursh, Esq.
520 Capital Mall Suite 700 Sacramento, California 95814 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814
Florida Power Corporation Mr. S. A. Brandimore Mr. Robert B. Borsum Vice President and General Counsel Babcock & Wilcox P. 0. Box 14042 Nuclear Power Generation DivisioM St. Petersburg, Florida 33733 Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Mr. Wilbur Langely, Chairman Board.of County Commissioners Citrus County Iverness, Florida 36250 Bureau of Intergovernmental Rel ations U. S. Environmental Protection Agency 660 Apalachee Parkway Region IV Office Tallahassee, Florida 32304 ATTN:
EIS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Director. Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460 Mr, R.
Shreve NeThe Public Counsel Room 4 Holland Bldg.
Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida Montgomery Building 2562 Executive Center Circle, E.
Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304
Toledo Edison Company Mr. Donald H. Hauser, Esq.
Director, Technical Assessment The Cleveland Electric Division Illuminating Company Office of Radiation Programs P. 0. Box 5000 (AW-459)
Cleveland, Ohio 44101 U. S. Environmental Protection Agency Crystal Mall #2 Gerald Charnoff, Esq.
Arlington, Virginia 20460 Shaw, Pittman, Potts and Trowbridge U. S. Environmental Protection Agency 1800 M Street, N.W.
Federal Activities Branch Washington, D.C. 20036 Region V Office ATTN: EIS COORDINATOR Leslie Henry, Esq.
230 South Dearborn Street Fuller, Seney, Henry and Hodge Chicago, Illinois 60604 300 Madison Avenue Toledo, Ohio 43604 Mr. Samuel J. Chilk, Secretary U. S.
-Nuclear Regulatory Cormmission.
Mr. Robert B. Borsum Washington, D.C.
20555 Pabcock & Wilcox.
Nuclear Power Generation Division The Honorable Tim McCormack Suite 420, 7735 Old Georgetown Road Ohio Senate Bethesda, Maryland 20014 Statehouse Columbus, Ohio 43216 The Honorable Tim McCormack 170 E. 209th Street Euclid, Ohio 44123 President, Board of County U.Comissioners of Ottawa County Port Clinton, Ohio 43452 Attorney General Uepartment of Attorney General 30 East Broad Street Columbus, Ohio 43215 Harold Kahn, Staff ScientiSt Bruce Churchill, Esq.
Power Siting Commission Shaw, Pittman, Potts &Trowbridge 361 East Broad Street 1800 M Street, N.W.
- Columbus, Ohio 43216 Washington, D.C.
20036 Docketing and Service Section Atomic Safety & Licensing Board Panel Office of the Secretary U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commiission Washington, D.C.
20555 Washington, D.C.
20555 Atomic Safety and Licensing Appeal Panel U. S. Nuclear ;egulatory Commission Washineton, D.C.
20555 Coumus hi.431
Toledo Edison Company Ivan W. Smith, Esq.
Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Dr. Cadet H. Hand, Jr.
Director, Bodega Marine Laboratory University of California P-. 0. Box 247 Bodega Bay, California 94923 Dr. Walter H. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830 Ms.
Jean DeJuljak 381 East 272 Euclid, Ohio 44117 Mr. Rick Jagger Industrial Commission State of Ohio 2323 West 5th Avenue Columbus, Ohio 43216 Ohio Department of Health ATTN: Director of Health 450 East Town Street Columbus, Ohio 43216
Metrapo4-tan Edison Company G. F. Trowbrdge, Esquire Dauphin County Office Emergency Shaw, Pittnan, Ratts & Trowbridge Preparedness 1800 M Street, U.W.
Court House, Room 7 Washington,, D. C. 20036 Front & Market Streets Harrisburg, Pennsylvania 17101 GPU Service Corporation Richard U. Hewad, Project Maager Mr. T. Gary Braugliton, Safety &ad Department of Environmental Resources Licensing Manager ATTN:
Director, Office of Radiological 260 Cherry 1ill Road Health Parsippany, New Jersey 07054 Post Office Box 2063 Harrisburg, Pennsylvania 17105 Pennsylvania Electric Company ir. R. W. Conrad Director, Technical Assessment Vice President, Generation Division 1001' Broad Street Office of Radiation Programs Johnstown, Penasylvania 1590 (AW-459)
U.! S. Environmental Protection Agency Miss Mary V. Seuthard, Chaiman Crystal Mall #2 Citizens for a Safe Environment A ington, Virginia 20460 Post Offlce ex 446 Harrsburq, Peasylvania Wl#A0 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Dr. Edward e.
Swartz Board of Supervisors Londonderry Township Governor's Office of State Planning RFD#1 -
Geyers Church Road and Development Middletown, Pennsylvania 17057 ATTN:
Coordinator, Pennsylvania State Clearinghouse U. S. Environmental Protection Agency P. 0. Box 1323 Region III Office Harrisburg, Pennsylvania 17120 ATTN:. EIS COORDINATOR Mr. J. G. Herbein Curtis Building (Sixth Floor)
Vice President 6ti and Walnut Streets Philadelphia, Pennsylvania 1A9106 Metropolitan Edison Company P.O. Box 480 Middletown, Pennsylvania 17057