ML19256B691
| ML19256B691 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/16/1979 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML19256B685 | List: |
| References | |
| TASK-TF, TASK-TMR G-712-9.9-1, NUDOCS 7908230272 | |
| Download: ML19256B691 (59) | |
Text
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FIfiAL REPORT OF THi-2 ACCIDEtiT AiSESSMEttT DGCI'tiEtiTAT'.0.l -
TRAliilliG PROGRAMS 3 PROCEDURE REVIEW 5/16/79
.n ep' O)9 026
')962 0 ~.72 y
a REPORT OF T!'I-2 ACCIDEt1T ASSESS!'E'!T DOCUt'E::TATIO" TRAlliI!;G PROGRA!!S & P?.CCEDURE PEVIE*f GUTLIF:E I.
I?!TRODUCT!0:1 II.
REPORT DATA COLLECTIO!!
III.
TRAI? LIT G PROGRAM EVALUATIO!! T!ESULTS IV.
REQUALIFICATIO!! PROGRA ' EVALUATIO!i V.
PROCEDURE EVALUATIO!!
VI.
CC !CLUSIOMS Atl0 REC 0!"!Ef!OATICils VII.
APPE?!DICIES 4
1919027
I.
IitTR000CTION As 'part of the ihree Mile Island Unit #2 Accident Assessment Documentation effort, Personnel Qualification Services (hereafter referred to as PQS) Company undertook the two fold task of:
A.
Reviewing, auditing and evaluating the TMI Unit #2 training and requalification programs and the facility Emergency Procedures (EP's) to determine whether by training and/or by use and execution of the EP's, the Unit operators had developed bias towards protecting equipment vis-a-vis protecting the health and safe +.y of the general public.
B.
Recommending appropriate modifications or additions to the training and requalification programs and the EP's based upon the results of these evaluations and conclusions.
Discussion of the task data collecting, review and evaluation results, conclusions and reccmmendations are described in the following sections of this report, e
II. REPCRT DATA COLLECTIOt A.
In order to perform the evaluations necessary to complete the training and requalification program review and audit tasks outlined in the report introduction section, the "ollowing data was collected.
1.
Auxiliary operator (AO), Licensed Control Room Operator (CRO) and Licensed Senior Reactor Operator Training Program descriptions and schedules (for review purposes).
2.
Licensed CR0 and SRO Requalification Program descriptions and schedules (for review purposes).
3.
Licensed R0 and SRO Requalification Program individual records and examinations (for audit purposes).
4 Copies of recent (11/78) NRC R0 and SRO license examina-tions (for review purposes).
5.
Copies of the taped intervius conducted by R. Long, et al, for the 11-7 3/28/79 shift complement, following the TMI-2 incident (for review purposes).
B.
Additionally, personal discussions and interviews were con-ducted with TMI staff members cognizant of the training and requalific1 tion programs administered to Unit #2 pa,.;onnel.
Individals contacted were:
(Parentheses indicate if RO or 5ROlicensed) 1.
TMI Training Oceanization a.
R. Zechman, Supervisor of Training 5.
M. Beers, Group Supervisor (SRO) c.
D. Boltz, Training Coordinator (SRO) d.
N. Brown, Training Coordinator (SRO) 2.
T!!I Staff
[9l9 {g a.
G. Miller, Station "anager (SPO) b.
J. Seelinger, Unit #1 Superintendent (SRO)
J. Floyd, Supervisor, Unit #2 Operations (SRO) c.
d.
R. Hutchinson, Unit 12 Shif t Supervisor (SM) 2_
II. REPORT DATA COLLECTIO?! (CO?lTINUED) e.
- 8. !!ehler, Unit #2 Shift Supervisor (SRO) f.
F. Scheimann, Unit !2 Shift Foreman ',SRO) 9
?f. Coleman, Unit #2 CP.0 (RO) h.
D. Olson, Unit #2 CR0 (RO) f.
M. Phillipe, Unit #2 CR0 in training j.
E. Curry, Unit #2 A0 "A" k.
R. Johnson, Unit #2 A0 "3" A selected question outline was developed for the T?'I staff inter-views and is included as Appendix "A" of this report.
C.
With regard to review of the Unit #2 EP's and selected 50P's, all of the EP's and the following SCP's were reviewed:
a.
2102 - 1.1, Unit Heatup b.
2102 - 1.3, Unit Startup c.
2102 - 2.1, Power Operations d.
2102 - 3.1, Unit Shutdown e.
2102 - 3.2, Unit Cooldown j919'030 3
III. TRAI? LING PROGRAF 1 EVALUATIO!! RESULTS Based upon the review and evaluati n of the data described in Section !! of this report the following results are provided:
A.
Auxiliary Ooerator (AO) Training Procrams A review of the guidelines for the initial A0 "C" training programs and the subsequent classroom and OJT outlines for upgrading A0 "C"'s to A0 "3"'s and then to A0 "A"'s shows them to be adequate with the following exceptions.
1 The A0 "C" OJT program implementation appears to be lacking in some continuity in that some "C" operators were too often not accompanied by a "B" or "A" operator during an inf tf al assign-ment in the plant.
2.
Classroom review of Standard Operating Procedures appears to be minimal particularly where the " whys" of the S0P steps are explained.
3.
Little plant " big picture" explanations including the function of the reactor, are provided the "C" AO's in training.
It was additionally noted that although "A" AO's have primary assign-ments on either Unit #1 or Unit #2 they are expected to be inter-changeable on short notice. No formal cross-training presently exists for this situation.
B.
CR0 Trainine Pecorams A review of the CR0 training program content, schedule and proficiency auditing shows the total program to be satisfactory in all areas, with the one exception being that the present classroom lecture on the theory of heat transfer, fluid flow and the thermodynamics of the plant cycle is minimal in content. The only existing instructor out-line is composed of the Unit #2 Technical Specifications pertaining to flux peaking. DNS, et al and some supporting Ba'J technical documan-tation.
C.
SRO Uccrade Procram The SRO upgrade program, designed to prepare licensed CRO's for their
!!RC SRO license examinations is a total self-study effort one conth in duration, with study guidelines, supervision and written audit examina-tions provided by training personnel. No formal lectures or oral examinations are administered.
It should be noted that results on NRC R0 and SRO license examinations had been excellent prior to and following the startup of both Unitf with 100" of R0's and 83.5% of S?C's who were examined receiving licenses. Table III-l expands on this success rate.
f919 031
III. TRAltlitlG PROGRAM EVALUATIO?1 RESULTS (CO?lTIflUED)
TABLE III - 1 R0 Att0 SR0 EXAMIflATIO?l RESULTS R0 R0 SRO SRn Year Acolications
_ Licenses Acolications Licenses 1974 14 14 13*
8 1975 0
0 5
5 1975 5
5 10 10 1977 14 14 19**
16 1978 10 10 12 11
- Include: cross-licenses on both units
[9f9'032"
-5
III. TRAINIrlG pRrG9AM EVALUATIOrt RESULTS (C0tlTl?UED)
C.
SRO Ucerade Procram (Cont.)
It is also worthy of note that the averag.e SRO upgrade candidate has had approximately 2h years experience as a licensed CRO, and two-thirds of all candida tes are flavy-nuclear experienced.
D.
Unit #2 Cross Licensing Traininc Procram In order to caet NRC requirements for Unit #1 SRO licensed personnel to qualify for Unit #2 SRO licensas, a formal, ten (10) week, in depth cross-licensing training program was developed and administer-ed in the summer of 1978. Appendix "B" of this report outlines the program, which highlights the differences in the design and proce-dures between the two uni +s.
The NRC did not administer examinations prior to issuing the Unit #2 SRO licenses, but accepted o, smentation from Tt!I management, stating that the individual candidates participated in the program and succes-s full y passed internal TMI written examinations. The flRC also review-ed t! ase examinations for content and applicability, flo SRO oral examinations were administered by the training depar+ ment or other internal auditors, and this was not an NRC requirement for issuance of the licenses. However, the SRO's licensed in the manner described administered orals to the Unit #2 CR0 license candidates prior to their ilRC examinations.
- * ~
- e Mt.9'0D 6
IV. REQUALIFICATION PROGRAM EVALUATIOM Appendix "C" of this report is a copy of TMI Administrative Procedure
- 1006, " Met-Ed. Operator Requalification Program".
It is i.cluded as an appendix because it is a fine exhibit of a rigorous and complete reqeblification training program which more than exceeds the NRC require-ments of 10CFR Part 55, Appendix A.
If implemented as well as it is described, a core than adequate requalification effort would be achieved.
The following paragraphs provide the results of an in-depth review arid audit of the implementation of TMI requalification program.
A.
Review of Annual Recualification Examination's Content The annual written requalification examination is a combination of R0 and SRO type e mstions arranged by categories similar to those on NRC examinations. However, some categories contain both' R0 and SR0 flRC designated category questions. As an example, Category A on the TitI examination contains questions for NRC categories A (Prinrioles of Reactor Operation) and H (Reactor Theory), because they aru similar in content. Appendix "D" of this report is a list of MRC designated categories and their titles.
With few exceptions, the 1978/1979 R0 and SRO written requalification examinations were satisfactory products, in that they:
1 Contained applicable questions for each type of excmination and category.
2.
Exhibited proper point value.
3.
Covered all aspects of the total TMI plant and its operations.
The exceptions to this were:
1 Concerning the ovarall point value for each NRC desicnated category with relation to the total SRO examination point value, the follow-ing categories were found to be icwer than a icwer % limit recom-mended by PQS* as follows:
Category "D" (Instruments and Controls) -1.9% low (11.17 TMI a.
vs.13% PQS).
b.
Category "F" (Standard and Emergency Oparating Procedure' )
s
-0.8% low (12,2% TMI vs.13% pQS),
Category "K" (Fuel Handling and Core Parameters) -2.2". low c.
(12.8% TMI vs.15", PQS).
- Refer to Appendix "D".
19'i9 034 7
IV. REQUALIFICATION PROGRAM EVALUATION (CONTIt!UEDI 2.
Concerning category question content:
Category A/H - no question regarding the principles of heat a.
transfer.
b.
Category C/J - no question requiring a discussion of the combined effects of reactivity coefficients, i.e., doppler and MTC; also questions C-3 (b) should require the SRO to explain the " whys" of the shape of the plots.
Category F/L - no questions addressing the RO's knowledge of c.
Standard Operating Procedures or the SRO's knowledge of Tech.
Spec, bases.
d.
Category G/I - question G-3 does not require that the examinee give the answer listed in the T'4I answer gauge.
B.
Review of Written Examination Individual Grades The actual and individual category grades on the overall R0 and SRO requalification examinations were reviewed to determine which individual RO's and SRO's required remedial training and examination as a result of requiring post-oral examinations. During the review of the Unit #2 R0 grades (Appendix E of this report) it was noted that of the eleven (11) RO's three (3) failed categcry "0" (Instruments and Controls) asd while three (3) failed Category "C" (General Operating Character 1 tics),
two (2) additional RO's obtained grades close to the failure grade which meant that five (5) of the eleven were less than or slightly more than adequately knowledgeable in this important area.
C.
Review of Individual Recualification 7ecords An audit of selected individual's requalification records was conducted and evaluated to determine whether or not compliance with the require-ments of 10CFR Part 55, Appendix A was met, both in content and completeness.
For purposes of this audit, the following six (S) licensed RO's and SRO's were selected and designated as follows on the audit form (Appendix 'F' cf this report).
!!ame Desionation E. Frederick RO #1 J. Kidwell RO #2 B. Smith SRO #1 W. Connoway SRO #2 19J9 035' G. Hit:
-e.
IV.
REOUALIFICATI0ft pROGRAff EVALUATI0ff (C0tiTINUED)
Based upon these individual's records review and evaluation, it is PQS' opinion that in general, the records are essentially complete and the program meets the overall intent of 10CFR Part 55 Appendix A.
However, two specific items of some concern were noted as follows:
1.
A review of the attendance at the B&W simulator for requalifi-cathn purposes indicated that Messrs. Frederick (RO) and Cor :oway (SRO) have not been at the siculator since mid-1977.
Additionally, it was noted by a further review of the records of the other licensed individuais on the 11-7 shift on March 28, 1979, namely Messrs. Scheimann and Faust, that they also had last retrained at the simulator in mid-1977 Only their Shift Superviscr, Mr. Zewe was more current, having attended in January of 1979.
It is our understanding that prior to 1978. RO's and SRO's were sent to the simulator annually, but early in 1978 a decision was made to the effect that biannual a'.:endance was adequate for requalification purposes.
In 1979, however, the annual attendance requirem.nts were re-instated.
2.
One of the SRO's whose records were audited failed four (4) categories on the written requalification examination admin-istered to him on February 15, 1979. However, to date, no required post cral examination has been administered to him nor has he attended any remedial lectures.
D.
Audit of Individual Exarc.4 nation Gradino Selected categories on the actual requalification examinations written by the two (2) RO's and four (4) SRO's were graded to evaluate the technical and point-counting adequacy of the TMI training group grading. Table IV-1 below tabulates these results:
TABLE IV-1
)919'036 SELECTED CATEGORIES EXAM CA7EGORY FACILITY AUDITOR'S TYPE SELECTED GRADE GRADE COMMEflTS PJ #1 D&G 100% & 80",
100". & 77.7" Sa tis factory R0 #2 CSE 70.4% & 84.5' 56.1" & 84.5f Sa tis factory SRO #1 C/J & F/L 83.S" & 84.1",
82.2", & 84.1",
Sa tis factory SRO #2 D&X 78.55 & 96.5' 76.0" & 79.1%
Unsa tis. on Category K SR0 #3 A/H & F/L 91.35 & 90.5",
38.7" & 91.3 %
Sa tisfactory SRO M C/J & G/I 91.9% & 87.4" 39.6% & 89.1",
Sa ti sfactory a
e a IV. REOUALIFICATION PROGRAM EVALUATION (C0tiTINUED)
PQS personnel have set a 5% difference between their grading during an audit and the facility grading; it was determined that the facility grading that was audited mat these requirements with one exception. On SRO #2's examination his answer to questions 3(a) and 3(b) of Category H (K equivalent) ware very vague; however, he was given full credit for his answer, which differed considerably with the gauge answer. Addf-tionally, for question S(b-2), he wrote a wrong numerical answer and showed none of his calculation but received considerable partia] credit.
Accordingly, the auditor's grading caused the category grade to drop below 80%, which would have caused a need for remedial training in the FSR program.
E.
General Recualification Program Observations The lead PQS auditor, during discussions with members of the TMI opera-tions staff and the license training coordinators, compiled information felt to be germaine to the total requalification program evaluation as follows:
1.
When the TMI operating staff originally utilized six (6) shifts, with one day shift designated as a training shift, the requalifica-tion program was judged as being very well implemented, both from an attendance standpoint and training instructor effectiveness. However, when the plants were returned to a five (5) shift operation in 1978, with the extra shift being assigned both relief and training duties, the requalification program implementation apparently became less effective than desired, the area cost affected being licensed R0 and SRO attendance at required lectures. Training supervision called attention to this attendance situation, but to no avail.
(Refer to Appendix "G", pages 1 and 2 of this report.)
In 1979, six (6) shift operation was re-instated, but to date, the effectiveness of the program implementation has not had the oppor-tunity to reach desired levels, attendance (or lack of it) again being the area affected. (Refer to page 3 of Appendix "G".)
In short, it appears that the momentum and rhythm that carried the original six (6) shift requalification program to success has not been achieved to date.
2.
Initial training and requalification training not administered by the TMI Training organization appears to be shift supervisor (SS) dependent, that is, some SS's are more training conscious than others. The effect of this is *. hat some shifts participate in group or individual training d%+ sions or "waat would you do if" drills more or less than other shifts.
i.
19L9:037
-1C-
IV. RgUA2.IFIN 10:1 FF 3 RAM EVALUATIO!1 (C0fl7I"f1ED)
Also, it s opears th=+
in addition to " day" shift supervisors being bogged ouwn with administrative duties, the back shift SS's also have considerable paperwork, further affecting their time for conducting training exercises, and, in fact, limiting their ability to leave the office to tour the plant occasionally during routine plant operation. This paperwork may consist of any or all of the following review or approval tasks:
a.
Surveillance Testing b.
Operations Surveillance c.
Temporary Change Requests d.
RMp's e.
Liquid and gas releases f.
Revision Review Book g.
Information Reports h.
Et al 3.
Some TMI staff members felt that requalification training was also dependent upon the amount of effort each individual operator puts into the program. Some do more than others, based upon the indi-vidual's degreee of initiative.
4 Criticism of the requalification program itself by TMI operations people may also be justifi.ed. Complaints are that many lectures are not updated as needed, that scme lectures are cancelled at the last minute, that certain lectures are just poorly prepared, and as is the case in most training atmospheres, that some instructors are not "3s good" as others. However, most operators also felt that the license program training instructors are overwhelmed by pape:mork.
It should be noted that when licensed people do not attend required requalification program lectures, packages of written review material must be prepared and sent to the absentees, and re-scheduling must be done. Thus, low levels of attendance result in high levels of training coordinator paperwork.
V.
PROCEDURE EVALUATI0tl A review of the Unit #2 Emergency Procedures and the selected Operating Procedures was conducted. As a result of the review, it is our opinion that the content of these procedures is technically accurate, with the proper and timely mix of immediate and follow-up action. However, like most procedures written in the industry, they are " cookbook" in nature.
Execution of the emergency procedures may be enhanced by the addition of scme procedural objectives. Such suggested procedure modifications are discussed in the Conclusions and Recommendations section of this report.
I919 '039' 9
=
VI. CONCLUSIONS AND RECOMMEMDATIONS Based upon the evaluations performed following the various reviews and audits described in the precedir:g sections of the report, the following conclusions and recommendations are submitted.
A.
It is our opinion that the operators of the TMI linit #2 plant were actually biased towards protecting the facility equipment vis-a-vis protecting the health and safety of the general public, and operated the plant accordingly. However, it is also our opinion that the operators did not consciously consider trade-cffs between protecting equipment or protecting the health and safety of the general public during the accident. Hence the bias is not an intentional one and it is enhanced by a certain training emphasis, but most importantly is a function of what is not in the training programs and not in the emergency procecures.
The bias exists because:
1 The operators (particularly !!avy Muclear experienced) feel they have "had it pounded into them" not to "go solid", which may have been a primary reason for reducing the High pressure Injection (HPI) during the event.
2.
The operators need additional
- ining to think beyond the cookbook procedural steps and analyze gncy conditions.
3.
The operators need additional
-sining to observe and believe instrumentation associated witn systems other than those involved with the emergency.
4.
The emergency procedures do not contain sufficient procedural objec-tives and discussion of the " whys" of the procedural steps.
5.
The operators are thought to have a "LOCA mentality" which lulls them into being on the lookout for the pipe breaks and not to expect or analyze transients similar to the 3/28/79 TMI event.
It is also our general conclusion that the effectiveness of the training and requalification programs has deteriorated, cost likely beginning with the return to a five (5) shift operation in 1973. However, because of the outstanding efforts of the training staff on pre-NRC examination audits and the strong self-training initiative and personal pride exhibited by the candidates thecselves, NRC examination results have been excellent.
B.
As a result of the evaluations which led to the conclusion stated above.
PQS proposes that the following radifications or additions to the train-ing organization, the training and requalification programs and the emergency procedures be implemented as soon as practicable, w
f9L9 040
_,3
VI. CONCLUSIONSAMDRECOMMENDATI6?ls(C0ilTJNUED)
Although we feel all of the eight (8) recommendations are important, an orde of priority is given, the priority based on our e"aluation of each recommendation's need for implementation. This order does not of course ' preclude parallel implementation of any or all of the recommendations.
1.
Trainino Orcanization Presently, the TMI Training Organization has two (2) operating groups, designated as " License Training" and "Non-license Training".
Figure VI-l depicts the basic organization and lists group responsibilities.
As of this writing, two (2) of the three (3) non-license training coordinator slots are not filled. One slot has been vacated since January and the second slot became empty with a resignation on 4 "ay 1979.
It is our opinion that the subject Training organization like the majority of similar organizations at other nuclear power plants, is understaffed and overworked. Some evidence of carelessness appeared during the review (ex. - refer to Section IV D) and this is often a sign of overload conditions.
This is the current situa-tion, and in all likelihood their workload will increase due to an expected upgrading of training and retraining requirements, due to the TMI event. Also, as will be apparent by a review of this report's proposed training and reoualification program modifica-tions, additional staff will be necessary to develop, administer and monitor the upgrade programs. The following specific recommen-dations are submitted, Restructure the organization as shown in Figure VI-2, to pro-a.
vide for the responsibility of a separate plant operator (licens-ed and non-licensed) training group. This would transfer the responsibility for Auxiliary Operator training to the present license training group, thereby ach ing continuity in the logical training development proces.
- A0 + CR0 + SRO.
b.
Provide a minimum of one (1) additinnal license training coordinator.
E Consider the provision of an additional records clerk to further c.
relieve the training coordinators from administrative duties.
An attempt to relieve the coordinators' scheduling paperwork would be most desirable, d.
Fill the vacant positions designated in the non plant operatar training group.
19L9/041 u-
Till TRAlfililG Records (Administrative Assistant)
LICEllSED N0ff-LICENSE TRAlNING TRAIllIflG i
e Supervisor o Supervisor e Two (2) Training Coordinators e Three (3) Training Coordinators W -
RESPollSIBILITIES:
RESPONSIBILITIES:
e R0 Initial Training e A0 Training s SR0 Initial Training e HP Training s SRO Upgrade Training e AN I R qu rements Training e Requalification Training N =
i 4
FIGilRE VI-l
Tit!
TRAlfilflG RECORDS (Ad;;;inistrative Assistant)
PLAfiT N0?l-PLAtlT OPERATOR OPERATOR TRAltlING TRAINIllG a Supervisor e Supervisor e Four (4) Trair 'ng Coordinators e Two (2) Training Coordinators RESP 0tlSIBILITIES RESPONSIBILITIES a A0 Training e HP Training a R0 Initial Training ANSI Requirements Training e
e SR0 Initial Training o Other Miscellaneous Training e SR0 Upgrade Training e Requalification Programs e-cf
-Om FIGtlRE VI-2
VI. CONCLUSIO!!S Atl0 RECOMME?IDATIONS (COMTIhuED) 1 Traininn Orcanize. ion (Cont.)
The experience requirements for the 1icensed training coordinators is considerable; thus it is suggested that the additional coordinator be obtained from the existing Ti1I operations organization, preferably be licensed SRO's or experienced licensed CRO's.
2.
Recualification Procrans Part 3 of this section a? dresses the subject of recommendations for the use of Nuclear Power Plant Training Simulators by the TMI reactor operators and senior reactor operators, as part of the requalifica-tion process.
The following recommendations are made in order that the existing in-hcuse requalification program implementation can be made more effective.
Each operating shift should have a standardized requalification a.
program implementation philosophy. The amount of requalification training is seen to be a function of the shift supervisors desires to conduct the training. To standardize the programs for each shift and to hopefully stimulate the SS's desires to conduct training, it is recommended that:
- 1) Training shifts do exactly what they were created to do - train.
It should be the SS responsibility to see to it that his opera-tors attend required cequalification program lectures. Unless an emergency situation exists, no operators on the training shifts should be prevented from doing training, by virtue of being assigned other duties.
- 2) Each back shift should engage in traiting exercises a minimum of 10', of the total hours worked during a shift cycle. This would be in addition to their r.ormal training shift assignment.
These exercises should be periodically monitored by members of the training organfration and should be at a minimum, a mix of:
a) Simulated EP drills (Section VI-4 of this report).
b) Discussion of reactor and plant transients, including observation of all instrumentation indicating effects of the transient, c) Review of technical specifications, b.
Whenever a licensed RO or SRO fails more than one category on his written requalification examination he should be required to begin remedial training or post oral examination within two conths gf his examination.
/
1919:0'44 VI. CONCLUSIONS AND REC 0ltPENDATIONS (CO?!TIfDfEDI 2.
Recualifica tion Procrams (Cont.)
c.
Periodically during a licensed RO's or S'<0's continuous re-training, program audits should be performed by knowledgeable individuals not assigned to the Ti!I plant staff.
3.
fluclear Power Plant Trainino Simulators (?!PPTS)
Discussions about the applicability and effectiveness of a flPPTS have been going on in the industry for over ten (10) years and its usefulness as a training tool has generally been proven, flPPTS use makes the job of training operators easier and also makes training easier for the operator himself.
!!RC requalification requirements allow for use of a flPPTS in lieu of actual plant reactivity manipulations. Utilities meet or exceed these requirements depending on trade-offs between amount of train-ing necessary for operators and e':enomic considerations. Hence, as regards f:PPTS usage for requalification purposes, some utilities send licensed RO's and SRO's to a NPPTS once during a two year period, others send them twice during the two year period, and a handful of utilities with more than a single unit station, operate their own simulators.
With regard to the T!!I licensed staff, it is reconmended that during each two (2) year period of an RO or SRO license the simulator train-ing be increased over the amount presently undertaken. Several options are open to achieve this additional training; PQS recom-mends that each of the following three (3) options be considered, and one chosen for implementation, a.
Increased 31W Simulator Usace Licensed RO's and SRO's would be sent to the Ba'l simulator at intervals of no more than every six (6) nonths, or four (4) times during the two year requalfication cycle.
Currently, it is our undarstanding that each year, the T?il operators spend five (5) days at the Simulator, but only 2h days are actually spent doing effective simulator training, due to reacquaintance time on the SMUD control panels and class-com lectures.
It would seem that due to the increased frequency of the operate,-
attendance, the reacquaintance time and classroom lectures could be reduced such that instead of two five (5) day assignments which now result in forty (40) hours of hands-on" training, this could become four, four day assignments resulting. in additional hours of simulator time. Additionally, if a'B&*.I fnstructor could be assigned to TMI prior to each visit, the tra,ining could be further streamlined and tailor-nade to fit,,Tl'I's npegs, f9 H 045 VI. CONCLUSIONS AND REC 0!'MEll0ATIONS (CONTit!UEO) 3.
Nuclear Power Plant Trainine Simulators (NPPTS) (Cont.)
b.
Additional BMI Simulator Venture It can be seen that f.hould all the B&W plants increase their usage of the existing simulator, an overload condition would likely exist.
This option sugges':s that B&W build a second simulator, funded by Met Ed, Duke Pnwer, Arkansas P&L, Florida Power Corppration and Toledo Edison, and operated by B&'.l.
c.
The last option to be considered is of course at the same time the most convenient solution and the most expensive, that of building a TMI simulator on the TMI site. However, once again, participation by other S&N plant owners is a possibility that could be explored.
It should be noted that only Option A is immediately available.
Nuclear Power Plant Training Simulators now have lead-time delivertes of approximately ther.e (3) years from the date of order.
As a final recommended consideration regarding the use of the B&W simulator, an audit team of experienced GPU System operator training personnel should be dispatched to the' B'.W facility to review and audit the requalification program administered to TMI operators. The purpose of the audit would be to:
- 1) Review simulator exercisas and lecture programs.
- 2) Review experience qualifications of instructor personnel.
- 3) Audit the proficiency of instructor personnel.
4.
Emercency Procedures While it is felt that the Emergency Procedures (EP's) and the Oper-ating Procedures are adequate in both technical content and organi-zation, they are cookbook in nature and the following recommenda-tions for modification of the EP's and their implementation are made.
During the review of EP's in initial training and requalificatic a.
training classes, it is our understanding that the objectives of each EP is discussed as we'l as the reason for the objectives.
We recommend that additionally, such discussion of or listing of these objectives actually appear in each procedure, or as an attachment to the procedure. The operators could then review the objectives on an ongoing basis during shif t training exer-cises. As an example, Appendix "H" of this-report is a portion of another PWR EP, which contains a brief discussion of their Loss of Main Coolant event.
1919 046
VI. CO.'!CLUSIONS AND RECOMMEf! DATIO?ls (CO?lTI?l0ED) 4 Emergency procedures (Cont.)
b.
Also during classroom review of the EP's, a discussion of expected instrumentation indication of all event related systems should be included. For example, for the pressurizer relief valve failed open procedure the operator's attention should be called to the observation of not only the indicated pressurizer parameters but also those indicated parameters associated with the RCS, the RC Drain Tank, et al.
Consideration should be given to providing a fault tree discus-c.
sion for each EP as the emargency condition may progress, simi-lar to the natural circulation EP developed prior to Unit 12 actually being placed in a N.C. condition.
d.
The implementation of the EP's is as important and may be more important than the procedure content. To this end we recommend that the TMI operator shift supervisors implement the following:
- 1) Conduct simulated EP drills in a team fashion, utilizing a set of drill evaluation sheets. These could be developed by the Training Organization with review by the Operations staff.
Appendix "I" is an example of one such drill sheet albeit developed by and implemented at a small B'<lR.
The concept can be used at all nuclear power plants, however.
The control room crew operates as a team but the Shift Supervisor is in total charge and directs the operation frem event beginning to event ending remaining in the control room, unless relieved of his duties by another SRO. This concept, of course, should be applied during actual emergencies.
2)
Direct the shift crew discussions of each EP's content with considerable stress on the crocedural objectives, so that the operators may be trained and re-trained to think through abnormal transients and enable then to recognize the total emergency and bring the plant to a stable condition as soon as possible.
- 3) Free himself from paperwork duties as much as practical'.y possible in order to:
a) Conduct requalification exercises on the back shifts.
b) Be able to leave the control room during routine plant operation and spend time on in-plant tours and assist in the OJT of "C" and "3" A0's.
l919~047
VI. C0!;CLUSIO?ls Atl0 REC 09MEil0ATIO?ls (CO?!TT!;UEDI To this end the TMI staff should consider the possibility of reducing the required back shift paperwork and/or pro-viding a back shift administrative assistant to the SS.
5.
Auxiliary Ooerator Traininn Procram The initial "C" A0 classroom program, as presently structured, pro-vides the operators with the knowledge of systems necessary to enable them to carry out their assigned duties. However, the following modifications are recommended to further increase their knowledge and efficiency.
The initial introductory training week should be expanded to a.
include an overall " big picture" explanation of the TMI Unit #2 plant and reactor. This should be minfrrum of eight (8) hours of instruction, to include:
- 1) A layman's discussion of how a reactor provides heat _ (similar to the way one explains it to his wife).
- 2) An overall presentation of how the total systems function to support the reactor and generate electricity.
- 3) A discussion of the imoortance of the A0 position and where, how and why the A0 can pro;ress in the organization.
b.
More supervised OJT for the "C" level A0 is needed, particularly in the early weeks of the assignment. This should be the responsibility of the entire shift crew, as the "C" A0 is after-all also a member of the team. It is suggested that a two step system check off be established for the "C" AO.
Initially, a "B" or an "A" A0 would teach the "C" a certain operation and sign off that it has been done.
Later, when the same operction is to be performed by the "C" A0, a CR0 or SRO would supervise and sign off for the second time, Additional classroom review of Standard Operating Procedures c.
should be provided the AO's in the way of explaining the " whys" of each procedure.
d.
Present A0 OJT training is based upon rotation thru plant A0 stations on a frequent basis. Consideration should be given to more lengthy rotational assignments, such that the A0 would be-come rnore familiar with each station before moving on to the next station.
A formal Unit #1 and Unit #2 cross-training program should be e.
developed which will better prepara "A" A0's to effectively function when, on short notice, they are assigned to the Unit other than the one they are primarily assigned,to.
This program,o
~
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VI. CONCLUSI0llS Afl0 RECOMMETIDATIO!!S. (C0flTIllUED) 5.
Auxiliary Coerator Training Procram (Cont.)
would be cnly for those AO's who would be expected to change assignments in this manner. Additionally, consideration should be given to curtailing this practice, except for non-routine situations.
6.
CR0 Trainine Procrams Based upon the overall evaluation of the T?!I incidant as it relates to operator training the following CR0 training program upgrade is recommended, An additional minimum of twenty (20) hours of instruction on a.
the knowledge of instruments and controls, particularly as they relate to the indication of the condition of the reactor and reactor coolant system. This training should include control room walk-throughs to actually observe instrumentation indication.
b.
Inclusion of the licensed CRO's and CR0 candidates in formal classroom instruction given to SRO's on the subject of the Unit #2 Technical Specifications (TS) including discussing TS bases.
In addition to the TS D?l3 and flux peaking lectures refer-c.
red to in Section III B, a minimum of six (6) hours of classroom lectures pertaining to the TVI Unit #2 applied principles of heat transfer and fluid flow should be added to the CR0 program.
d.
It is our understanding that CR0 program lectures regarding the understanding of abnormal and energency operating plant transients presently exist.
These lectures should be review-ed and upgraded as necessary to reflect the events of 3/23/79.
Additionally, selected transient traces recorded that morning should be reviewed and analyzed as part of this lecture program.
7.
3R0 Training Program At present, no formal classroom SR0 upgrade program exists.
Although our opinion is that the self-study program is adequata and results on flRC SRO ifcense examinations are excellent, it is recommended that a more formalized SP0 upgrade program be develop-ed to include the following:
Prior to the beginning of SRO license candidate's self study a.
program, the following lectures should be administered.
- 1) Specific TMI plant and reactor operating characteris-tics (approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />).
e e
VI. C0tlCLUSIO.'lS Atl0 RECOMMETIDATICil5 (C0!!TitlVED) 7.
SRO Trainina Procram (Cont.)
- 2) Radioactive' materials handling, Disposal and Hazards (approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).
- 3) Administrative procedures conditions and limitations (approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />).
- 4) TMI emergency plan (approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).
b.
In addition to the present SRO level written examinations, each candidate should be administered an SRO level oral examination.
This examination, approximately four (4) hours in length, should be administered by members of the training organization.
SRO licensed operating plant staff, or other qualified con-sultants. This oral exanination should be completed one week prior to the NRC examination.
8.
Proficieciev Examir:ations In addition to the examinations administered to the RO and a.
SRO license candidat.es by the training organization TMI Sta-tion management should consider periodic training program audits by knowledgeable individuals not assigned to the TMI plant staff.
b.
Members of the TMI operating staff have suggested that the one-on-one examinations administered to license candidates by TMI t:cining staff or ?!RC examiners do not place the candidates i,1 stress situation similar to that existing during a real p1 c.t emergency. They further feel that although the BS'l sS.nlator is an excellent training device, it does not carry the operators past the end of an emergency event and there-fore does not put them into more stressful situations (i.e.,
"I've had my LOCA - let's go on to the next drill".)
PQS supports this theory and can foresee the possibility of the simulator programs (training, not machine) being restructur-ed to make the operators carry through to an Emergency Plan, as an example.
Additionally, some members of the operating scaff suggest that a board examination similar to that established in the flavy fluclear Program oe used for selected 90 and SRO license candidates and for certain requalification oral examinations, to create a further " stress under fire" atmosphere. This board could be made up of the Unit Supe. intendent, Operations Manager, a Training Coordinator, a B&'.1 design engineer, the Reactor Engineer, an outside training consultanNa% etjygyi.
as daemed appropriate.
'E 7 7 7. V J u VI. CO?tCLUSIO!!S A!!D REC 0f t?tEtiOATIO?is (CO:ITI5!!!ED) 8.
Proff:iency Examinations (Continued)
PQS reco:T. mends that such a board typ examination be considered, but stresses that these examinations would be in addition to, and not in lieu of, the present one-on-one examinations.
19[9'051 APPENDIX A A0/R0/SRO INTERVIEWS NAME:
POSITION:
1.
Regarding the training you initiaily received to qualify you for your position and/or license:
a.
Did you consider it adequate? If not, why?
b.
Which areas were stressed most in the program?
c.
Which areas do you feel should have been stressed more?
d.
Do you feel the NRC examination was a good audit of your ability to safely and effectively carry out your assigned duties? If not, why?
2.
Regarding the retraining you are continuously undergoing:
a.
Do you consider it adequate? If not, why?
b.
On your shift, what drills or quizzes are conducted? (Other than the TC audits.)
Mcw would you rata the quality of your most recent simulator c.
training, with respect to: Expl a i n.
- 1) Simulator capability
- 2) Program adequacy
- 3) Instructor quality 3.
Regarding the Unit 12 emergency procedures:
a.
Do you consider them to be adequate? If not, why?
b.
Co you understand the purpose of each procedure that has been written?
19iSF052
1:
TM78-127 METROPOLITAN EDISON CO M P AN Y se,y o, c.,,,,,, rue unm.
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TMI !!uclear Station Subia:t SHIFT SUPERVISOR DEVELCPi.3IT PROGPAM to:stien Middletown, Pa.
UtlIT II CROSS LICEllSIflG TPAI!1I?lG FROGRAM Data June 1, 1978 Frern D. A. GCCCMAft Tc M. J. ROSS J. R. FLOYD 7
The follcwing Training Program has been developed by the TMI Training Depart =ent for a Unit I SR0 licensed individual to qualify for a Unit II SRO license. The program is designed as a self-study prog.am with written and oral quizzes being administered by the Training Department to monitor the individual's progress. Weekly study assignments are designed to cover specific areas. For example, the assignment for the fifth week includes the STS section on the reactor coolant system and RCS references in the Unit I/
II Differences Ecok and Horse Book. The Shift Superiisor Trainee is also expected to select for that week those tasks frca the Practical Evciutions List that deal with the RCS.
This training will culminate in the Shift Supervisor Trainee taking a Unit II STO level written examination. The exam will be prepared, written, and corrected by the TMI Training Department. The program documentation and exam grades will be forwarded to the flRC for revikew in order that the Trainee's Unit I SRO license may be ar---ded to include Unit II.
ff,P fp--
e-Donald A. Goodma Group Supertiser - Technical Training CAG/drg Attachment o
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R. U. Zechman D. J. Boltz
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15 point - practical evolutions (2)
Turbine Generator & Auxiliaries (3)(4)
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Solid, liquid, & gasecus waste systems (3)(4)
Oral Exam #1 Ucek #3 STS Section 3/4.2 Power Distribution Limits (1) D. J. Bolt:
/
/
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Week !4 STS Section 3/4.3 Instrumentation (1)
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Reactor Coolant System (3) (4)
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Written Exam #2 l leek #7 STS Section 3/4.7 Plant Systems (1)
D. J. Bol t:
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.v T* ~ PEftICD, ASSIGt:MEtlT TRAIfil?!G CCCR0I?!ATOR di5 Section 6, Administrative Controls (1)
D. J. Bol t'-
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Week #10 STS Review (1) g/7, g/ggg System Differences Review (3)(4)
Written Cross License Exam f;0TES:
(1) S t.22 d. Ce Tech. Specs. - Unit II (2) f, Practical Evolutions List - Unit II (3) ' Unit I - Unit II Differences Book (4) Unit II n:r:a i:r.ck e
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In addition, the implementation of this program conforms to 10CFR50.-..
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Pre-planned Lectures j{w.-
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On-the -job-training
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Records
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' 5 Accelerated Requalificaticn Program
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7Requalificaticn Program Administration l - T.".
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1.3 Pregn.m Schedule c
,c The requalific2 tion program described herein will be implemented at a specified date within g0 days after receipt of an acerating.
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04/11/77 license. iiarchil Jant subsequent anniversaries of this date, will.
~
be considered to be the starting date of each annual cycle of
.J. :I.
requalification program operation.
J The Metrcpolitan Edison Requalificatica Program consists of four.l ~-.4:r.~
5
-, p,- ;~[ 2 3'.. %,{.
.f interrelated segments which run cencurrently. These segments are: ' " -W. ;- ' ~ -
.1)
Operational Review Lecture Series (OR)
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Fundamentalsa.nd. System'ReviewPrdgram.(FSR) i.$,N...S,.WTt.47.
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.V4}c Annual:.Evaluationixaminaticns.
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Nrelated to the Three Mire-Island.Staticn.2 As'part, of1the. OR Ser.ies,.ff..:.S. ;c.:r "%.g n
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-selected FSR topics are presented. FSR tcpics are selected in C.
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. indicate. that.emphasisiin scope and depth of coverage
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1.5.hf-CR lectures are scheduled.for a minim.m cf 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year.' M'. ~
- .W.1
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. On-the-job-training is designed to insure that all licensed personnel operate reactor controls and participate in major plant evolutions.
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Records of all'.cn-shift perfor=ance are =aintained and pericdically ?f$.'_'_'
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reviewed by supervisory personnel. The ~ annual evaluation examinations
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simulate the written add oral.examinatiens administered by thef.~. f.'E+3.
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itiuclear Regulatory Cc mission:. performance en these>annuaT7~evaTuation.W:ZJ T
f examinations determine thep-u jh-QdC.
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relleving twelve month requalification pericd.- Z. ~. ::;W. n;E.3rf.'
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^L Each licensa holder will cc=plete all OR and FSR requirements en an - I'7 E
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a%*
l annual cycle. The On-the-job-training is conducted throughout the two year term of the individual's 1icense. All required on-the-i jcb-training will be co cleted prior to license renewal,.,
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04/11/77 A statement of Requalification program participation will be 'ubmitted s
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with each license ranewal application. The requalifigtion ' program ' 7
~
is designed with fixed performance standards and specified remedial actions. The program. results and records are fully auditable.
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2.0 REGUIREMENTS '
~
2.1 Operational Review (CR) Lectures Series
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Curing each year, personnel shall attend the Operational Revf w. -
-(OR)? LectureGSeri'eMordtheffcIlcwing-basisic,f.;.a$Tay~en.. m..QW
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-G.-.g instructorspexcept-ta. the extent. that their. normal: duties #..:-c,.lT r:q%y. :.
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-4 R;h00 (ecture Series attendance is requiredi f'all licensedP-WMtih-
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". W:.39 assignments.
. se:
e The folicwing topics shall be covered as a minimub during the OR Lecture Series each year:
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(a) Reportable: Occurrences.3 p Vy, ::a..
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9 (b) Unit Mcdificaticns g
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,(f) Technical Specificaticns
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(g) Major Coerational Evolutiens (such as refueling).'
(h) Applicable per'icns of Title 10, Chapter I, Ccde of Federal Regulatiens i
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04/11/77 7
. _(i) FSR Pr gram Matarial ____. _.,
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Additicnal topics which may be presented include:
(but are not 1.imited to)
(a) Operational Q/A.
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- (c) Operating Experiences - Reacter Safety and other pertinent NRC
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publications
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N LectureszshalT'be heTdicn'."a.:ccnt1nuing-basis a
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' 3inimum.-of".6G'~ scheduled. hours.per requalificatica program. cy.c.1e.'J.
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s - ~: 6 ter projh.elidep'erations_ Rec'ceds of the topics.1, covered;irr;e M
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. i.sessicrr wilI. be ca.intained. by.the Train,ing: Depart =enterg.Attendanca..v;.m. cz~
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..,..of all licen. sed perscnnel will be recorded. _ Absences will be made t
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r sucerviscrv cewa4 or the technical staff. Pericdic evaTuaticn.: ' '.e'.w.,.-
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quir:es covering the centent of the CR lecture series will.be c
c ;..,-
i administered. The quiz:es may be ad.ninistered in.either the closed s
book or open bcck format, as class recm, or en-shift qui::es.. If -
~
i
~
an unsatisfactory grada (less than 80%) is received, makeup sessions.W.:. '
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with assigned instructors will be conducted. The makeup session
.. Ou will conclude when an oral evaluatica is satisfactorily cc=pleted.
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' The centant:af the c1.ifwi1T.'be diMerent for RO and:SRO.:Ticense p,l_?%6-E'r
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...j.g..g holders and will reflect the tcpic areas and degrees cf responsibility 3F.9,...'
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needed by-the license holder. Examoles of the caterials to ba used JWP.-c
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during the CR lecture series are:
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. Revision 2
.3..
04/11/77
--.n....
'(a) Unit Records *and. Lags
~~ -. ;
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(b) Pertinent Coc::unications to and frcm the NRC C\\
M ('D be g
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(c) Unit Procedures and Changes.
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D *
(d) Test Results
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D
' R".k r (e) Applicable ~ Training Prcgram Matarials
%q'n' 2. ?_
Fundamentals and System Review (FSR) Program
- .;..-: p:.
d During eacSyear -licensed persennel shall participate in thi.%.
.#u..
$--ps$, JD:_-
5 &-S A M ?i M.?..>:#.:26':2 v - :.
c-q. : mW..:. :O:-25t=w.d "Fundamentars: and Systems: Review (FSR)'Prcgram.baseicn theiWannua 77.L:wN;-
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..:s$,.&.+C:s;.Y;. written. examination.: scores as identified in Section IV '. Eva.luations
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7The-FSR Pr~ogran may consistfofipre-planned. lecture series, self,.
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.?Qstudy.assignmenti2i:oss.-
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th. iy.d..
- technicaT,T fitstructo.rsr and' evaluatien-quizzes'.E.The study assign =ents..sii.R.'.
.M,. and pre-planned lectures will be in. keeping with the license level ~ './'.
L
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C;:n & v$yz.: M.&i.;.-lCB5&%~pE-Ay;;,%-Mis., ;:-n.: -@.4 ;
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of ~the individual Ticense~h61 der.
Individuar study assign =ents,'
~~
~
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. films, and video tapes will censist of no mo.re than 50% of the FSR O
-4.
.a Program.
Pre-planned FSR lectures shall be scheduled in those areas where annual operator and senicr operator written examinaticns indicate
. m..;
- s that emphasT}s"in secpe-and depth of coverage is needed. ". ' -
.~
Any er all of the folicwing topics may be included in a particular year's FSR Program: '
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a.
t. 7 m..=
. -. ('a ) PrincipTes or_.0peration ~
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(b) or rac1Tity Design
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, g-7 (c) GeneraT Cperating Charactaristics
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.j (d)
Instrumentaticn and Control (e) Safety and c.mergency Systems Including Unit /Statica Protecticri Systems 1919.062 e. C.
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'C44T.1/77 M ;M ':-
(f) ~ Normal and Emergency Operat.ing._Precedures --
(g) Radiation Control and Safety For Senior Operators the FSR Program will also include:
' [.
,.3 (h) Reactor Theory *
- b- (..
~
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(i) Radicactive Material Handling, Disposal, and Hazards. -
- h. E.W.E[
B9 (j) Specific Operating Characteristics 9
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(k) Fuel ~ Handling and Core Parameters
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1.1):: Administrative,:-Precedures, Ccnditicas,..and.: (imitationsT.p,..,.. pyW.S.
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-h Performance.of FSRJassignments will be.detarmined thrcugh written. eft;1l. A:
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- evaluation quizzes...,.Tnese quizzes will be specifically?gj3.. y afv.'.,y, directed".. : M G 9 3:c.
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.toward RO or SRO knowledge requirements tae quiz:es r.ay be-administered C
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.....e grade beicw 80% is achieved by a license holdar,' a deficiency. is
. ~,....
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assigned and the license holder will be assigned an accelerat'ed
~
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N. - -
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I 2.3 Cn-the-job-training i
I During ther two-year term of his license, each licensed operator
' ->ssy
.t @
snall participate in en-the-job-training which has the folicwing.
i goals:
1
}
~.
,..-+..,:
.-:~
e a.
(a) Each licensed reactor operatoror senior operator shaIT.fparticipate,j'.i
...x.
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in a minimum of:- 10 reactivity::anipulatians as deficed. in. this.,_.,gg,m..
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,j section of the requalifica:icn program.
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(b)
Each. licensed reactor operat::r or senior Operator shall participata as apprcpriata, in acplicable surveillance testing, system
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checkout and equipment operation based on license level and
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relevance to the area of license responsibility.
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~ Revision 2'.3...
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~
~ 04/11/77
~
(c)
Each licensed reactor operator.or.senice. cperator. sha.ll review _.f. _
s procedure changes, unit modifications, Nchnical specification changes, reportable occurrences and incidents either on-tha-job or during sessions of the OR Lecture Series.
],. -.
- .,J -
8
~ Each licensed reactor aperator shall manipulate the unit controls..,.':.c to effect reasonable reactivity changes.
Each licensed senior reacter operator shall either manipulate er direct the manipulaticn N.3;- ;t
.. ~..
f.
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-MoiEthe unit con. trois.i..to.reffect reasonable reactivity changes.r.:.'.u'.
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~q,e q, Reactivity. manipulations which demonstrata skill and cr familiarity '5.3WI e
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n%!Tiith reactivity centroidsystems and which are. credited to meeting.r.' q6,s.
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wi N.ca-the-fob-training:g.l.1. include but.are not.1imitad. to:c.?F,@...
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control station in manual.
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Contrcl?. red manipulation frem subcritical condition ~ to point r'
'V, of adding nuclear heat...
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Soration and debaration maneuvers involving control red mani-
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pulation.
4.
Turbine startup and shutdcwn.
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Reactor. trips and subsequent acticns,
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The participation of licensed persennel in the on-the-job pregram.
will be reviewed quarterly by apprcpriate supervisors to insure.
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that cperators participate in a variety of evolutions - If diversity.
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s.
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,'C Nof operations is lacking % specific assignments may be made to '
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ensure wide-cperatcr experience..
?
Included in the folicwing list are exa.%ples of additicnal cperations 4
3j which may be censidered in this category. These samples are not. to 1
?!
be censidered for reactivity manipulation credi w.
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04/11/77 1.
- Surveillance Test 1ng.ncluding: - -
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Containment Spray System
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Sar. ty Inject 1cn
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Emergency.D.iesel Generatcrs ~,:
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Chemical. Additien System
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Makeup and Purification System Operaticn
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Feedwater Systam Oceration-
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l 10.
Portable HP Instrument Use.
Licensed perscnnel, whose jcb assign =ents are not directly related
.[. '
. ;w;C.. -
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I to unit operations will' actively participate in centrel reca' operation G J '- l an average of 4 hcurs par month. During this period thesa, licensed
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personnel. will participate. in whatever-activities are in. progress.. wg..f.E..-
a.
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A simulator may be used in meeting the requirements of.this section '7~ %,'?
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The use of a simulator-te. meet the en-the-job training sectien of' 'M@M. -
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. 0 -..,.2( M t
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the prcgram must be reviewed by the MRC pricr-to implementation.
- v. -... -
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.1 The follcwing standards apcly to the evaluatien of en-the-jcb
~
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cericrance:
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Revision 2,.
C1/11/77 l... Quarterly review of-operations-particiaaticn will be.cade by
. g..,
the appropriate supervisors. The revie.s must indicate a diversity of experience.
If this is not demonstrated, the operator will. be scheduled for additional operating experience.
.^'
c
~
T'-
2.
' Quarterly review of reactivity control manipulation (RO) or
?.:.0. -
direction (SRO) rust show satisfactory progress tcward the 7'~~-
minimum of 10. operations as defined in this secticn. If
- y;%.:n..-:.~. 5 w.s-.N&s-m-::.s.>..$?'7-satisfactory progresssii... -:.not
... ?.:, w..?
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y:s;s: assigned additicnal:centrol recm. operations..or may acccmplish N
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-(.WF.S therrequired reactivity c. hanger e.n.a. simulator... -
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. Annuat.'revlemofilicensed perscnnel w.ncse.aob assignments are s--i-t.% ;..
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etges -
ci,q. g.y:,-.3. :.....;
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not; directly.related. tc unit cperations must show a' minimum.of
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48 hcurs of unit operatica assignments per year. If this is 12$..% s 5593.v.~,l.Qs.r:. - :n.';..\\.*Di&i:-4:e. L m.y M. s.%;~ '...: k; y -
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97.,c..-cc :.' nct-:cci::plete, perscnnel will be assigned to active control y
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7' 7 reca ' duty until the time is cada up.. A simulatcr ::.ay be used
~ x '..
to. complete. control rocm time..,
Q ~.,:. '.-
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u 2.4 Annual Evaluatien Examination Evaluations will be conducted on an annual basis as follows:
- k
~ '(a) Art annuaT written evaluatica examination will be given to all -
~
licensed operatcrs and senior cperatcrs prior to the ccmpletion v-:
of each annual _ cycle. '
, i.b m '
. ~ ?%
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' (b) An.a'nnuar orar evaluatien willebe administered to aIT licensed. ";;'c:ff-
- :..;.: ~.
2.c,:. -
v :. '. :.:.
operators ano, senior operatcrs prior to completlen or eacn R-
- e. -
- v. _...
annuai cycTe. -
The annual written evaluation exr.inaticn will be administered to
~
f all licensed perscnnel as set forth in the follcwing guidelines:
1919'066 lo.o B
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' 1 C05':';*
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m : Revision 2 e7.
~
- m....
04/lT/77
~
~
1
.The. examination.wi;11. siculate_.the examinaticn normally administered by the t'uclear Regulatory Ccr:::ission.
2.
Reacter Operators will take Sections A through G of the examinaticn
.:u.c while the Senior Reactcr Operators will take Secticns H.through
~ ~
J...:..
.r L and answer selected questions in Sections A through G5.,-
' m" W', -...
t
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The examination, examination answers and a grading key will be
-. j prepared in advance..
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~4.:rn.The examinatien-results: will be used t.o identifyispecific.,*F
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- .s.. -~
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ri~es topics.c be covered' by each li' censed.-individua1M.... 9C
=, u.n.
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during the.subsequentrannual requalification program'cycTe~_
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.5.h;.The..examinatien wilt be. administared and. graded by'.a,mmber-of..;ff.(Gdy
's
- St..
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q the station. technical staff, station managementf staff;". training @p,t.'?.J
..z. g q..
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.y department supervisor, or consultant.
'W-
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- 63(nThe persons responsible-for the preparatica of thle examinations'kg;".g.G
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' V and answers will be given credit for. passing the examination. ;r..' '
.r. ;..;~-
The annual oral evaluation examina*icn, using a_ checklist, will be
~
~
a.+; p;jy.
. :g~..
.,y
^
administered to all licensed personnel. The oral examination will
~~
cover the following areas:
(a) Action in event of abnormal conditions
~~
. jf.:.H.,j.1 (b) Action in event of emergency ccndi'ticns T
- p. J (c) Response to unit transients
,9,,, c J'
(d)
In s trumen tation s i gnal, interp reta ti c.;
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(f) Unit T.cdificaticns.< '
6 (g). Technical specifications
-.c.r (h)
Emergency plans r nD D
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Revisica 2-04/11/77
~
The following standards apply to the annual evaluation eximinatio'ns: - ~ ~ ~ ~
1.
A license holder who scores higher than 80% in all sections of the annual written evaluation will not be required to participata -
in the' FSR program.
' ~ -
u.
2.
If a.. license holder scores less than 80". on any sections of j.-
the annual written examination, the license holder will attend
.,s.
4;.f.4,@fft' 1."E the FSR program r' elated to failed sections.
,i.: '
.m
.. %....L l-; M hh.y.w:4&h,w?.
- W*W
.;-e +; R.ph:f.14L%in::
' 7
'Fi.n
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If a license' holder scored belcw 50% in two or more sections, y,_ jQ 3r '
y?;p -
. n
- _
- yk_.u..
'.. :,t...
.: a....,. 3% _.;A:
,JS i+-A;*of'the annual written examinatica, the license holder will.be
. j-l
..,.u, ;_w.;...g.,
- !.V. m
&.-Q.
, ga g'.,p..
.pyy.=
. y.g..
T' giver an cral."axamination and evaluation by' the Superv.isor'of'.-"
.:.J;..
X $.. %.-.$..@... 0pe,ra.,ticnsWSupervisor ci".Trainingscr.other suit
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.... =. -
- m
. -....,.,,, n.,..m
- 6. ;,,. -
,..,4,. -
".. persons designated by the Unit Superintendent....' This. examiner ' s-;
. +....
.w.
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i.
willi, based on.;the.tresults of his., examination,. cake.a recem-
.:... n.e.
- $g ' ' @, % n? W M 6t W W.i & " R= *W CL cc &~.5%K*
b L
- 3.Q '-
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.-( : y:r -;'
- 2
- ~ mendaticn in writing to the Unit Superintendent, that. the-
.e.c.
v.
.:,: e,... -
"W,..
Operator.either :-(1). be relieved of his respcnsibilities and
.,,c; ~
e.
- ~v..
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a
'1'
.j.
- ?.
ente.6an' accelerated training program cr'(2) be permitted to remain on shift while participating'in the appropriate requalifi-cation FSR program with suitable tutorial assistance.
u.
4.
An unsatisfactory evaluation on the annual oral examination
'~
will require that discussicns of deficiencies take place j
between.the license holder and either the Supervisor of Operations,
-:.&;;p..
'. :1
. q..
- g., _.ny
.1,.
..w Supervisor of Training, cr other suitable quali'fied person.
..'G
-. s
- . cc+.%<
2, O.m...
ii...
a.
. g.. a...
w, Jy-designated by the Unit Superintendent. A second oral evaluation T
- z..
1 examination will be ad=inistered.
If perfer=ance is again 1
l unsatisfactory, the license holder will be relieved of respcnsi-e i
bilities and placed into an accelerated requalification program.
1 i
12.0 gjg 068 S3 b
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- 1 C06.1 Revision 2.':+ *" T a..
c-04/11/77 5.
If an individual receives a grada of less than 70" overall on the annual. examination it will be mandatory that (1) he be relieved of his licensed duties and (2) enter an accelerated requalification program. Upen (1) successfully passing a
.. I.
~
second written and oral examination and (2) certification of
~
.,.y.c satisfactory rating being sent to the.NRC, the individual will
\\..
,?.
be returned to hist. licensed duties..
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.. c..~. %.:
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.Recot,ds of. Iicensed personnel;;f-
.c, TI'_
perfor=ance on. al.1. writtan.. evaluation
.m, ;... 7
,, c....,- g.
- y.,,...e.;::,,..,..
..'..<_.,_m n e
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7'
-i examinaticns and qui :es shall be available for NRC examinatien.f.or-1.t..fi,..4 "
s,
. -;.y.. a
.., +....
.. r.. i,......
.. _;.:.;..y_
e_.
- i-5 ~'J v5the-ts annual Trequaliffi~ cation cycles. p. iore
- tchlicenseir n..:; x.en T
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q,,,,9_ g gt y.;4... y.,s.;p:-
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include: yc,:.t~~ g;m:;....m....
s r
. r;::-
" application:.:.=These records shal1..
. p +...f.e
.T., w,,
1.
xaminatica and quiz questions.
m F %.e g-:..
..;.+ c.--:.-,t.;...-;.y y.;..,;.. w.:g;5.:.q. ;ipy f. ;::,,9Pg,. Q.m:.y:--m.. :e...f;;p
.. L.:: j 3..
.o
..v.o 41 -
2.
Answer sheets and grade keys
~
.;r-S.-.,,b..?.%-7
. - 3.7. Examination papeYs'. an2 work sheets'-
.m..,.....
[..... N. r: N.,b..y ' 9kb..
~
l
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~
g.
. Records of participation in all CR lecture and FSR programs will.be -. -4
.. _.34.-;y.. 3.-;. =qp.
available for NRC review for the. two annual requalification cycles.
~
price to license renewal application. These records shall include:
...~..
1.
Attendance Records.
c 4
~ gr...,
'~
.-3 2.
CR Lecture Ccntent
?.
,:.a.
3.
FSR Assignment
./ J'
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.; ;.;-:9:._.h D.3 y 4.
Absences and Makeup Sessions'
.'. c.. W $.. - 5.
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- M;. s [p (6 :m..
-.M
- 3..'..:,n..,..,;,9 7.; 1,.M;
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- 2.
Assign =ent Checkor.. Lists gt.4-
-Q y
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., fe
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r 3;
e u;. ;-
5.
Cocument Review Lists yl..
. s.
P' :c.,
Records of annual oral evaluation examinations shall be made available for NRC review for the two annual requalification cycles prior to
~
1 4-license rt.ewal application.
1919'069 i
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. p; Revision 2 04/11/77
~
' Records of a-il-on the'-job activities shall be available for-NRC '
review for the two annual requalification cycles price to license renewal applications. '.These records shall include:
1.
Reactivity Centrol Manipulation 2.
Equipment. Operatien.
~
. a 3.
Simulator Participation S.,. y..,
4 1.w s.
1.2...
A summary rederd will be ma.intained on. each license holder for--the.
. m:$N'.
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- 1zs.;;;a. $
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.n duration or his'. employment.
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- Ane operatcr wholoefnct. clear ceffciencies assigned due to. terformance "
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wilt 2be.-_-reTieved of r&.espc.Wollities.and. enter a full time accelerated !.'
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F' the program duration and content will be dictatad by the nature of p
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.the. deficiency.. Progra.m. duration will be determined by indiv'idual
~
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. performance? When the-lic~e,nse holderdis.(1) abl.e tc satisfactorily
~
~
~
,c pass an equivalent written or oral examination and (2) carcification of his satisfactory rating is sent to the NRC, he shall resu=e his
.,;M sr...,,
on-shift ~ responsibilities.. During the pericd of accelerated requalifi-catien, attendance at the OR lecture series is required.
If the '
~ license holder is off-shift. for more.than 4 months, Section 2.7
. ;.u.m
- d..
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" dealing with leng 2yJabsences acplies.
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Y 2.7 Four Ment.tAbsence Program -
~
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Qm If i licensed person has'not actively carried out the functions of -
his license for a pericd in excess of fcur ranths he shall:
(a) Review all material presentad or scheduled to have been presented I
ir. the CR lecture series for the pericd of inactivity....
14.0 e
"1919 070
_. m r_
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. ; rg-9 Revision 2..
+-
. Q
- 04/11/77
-..(b)__Je given an oral examination en the applicable Secticn of the w.-.
OR 1ecture series and current unit status.
If perfor.ance on the oral evaluation is unsatisfactory, the individual
- r will be placed in an Accelerated Requalification Program in accordanca'_,.
- y...:
.:_,a r.
J l.:
w.T -
with Section 2.6.
. -...... - e.u p.
Upon receipt of a satisfactory rating the licensed persca shall.be certified by the Supervisor of Operations, Supervisor of Training '
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- -(The certification cf.! satisfactory rating. wilt he transmitted'.to theM.. P.G...-
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$ flRC. and onlytafterip' roval' by the NRC shallitha operator' bd: returned ' r) '.j;.:
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2.8 ;Nawly Licensed Operators..
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j.: gr._... (., f Newly licansad operators, upon receipt of their license, shall T enter the program and. participate in the annual' program cycle. M' ~ 4:;-9
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New operators receiving their flRC license less than six months-l 1.pricr to the. annual evaluaticn examination will be. required to..._f..... ' ' :.
.... g._.m.m.. ;._,..g.:.m.. :.. : -
. =.
l attend the ap;:ropriate OR and FSR Programs but'will be excused from i.
taking the current annual evaluatica examination.
Mcwever, he will
.be responsible for taking-all other annual evaluation examinations.
.J.f.
W.
3.0 RESFONSI3tLITIES - REOUALIFICATIO*1 PROGRAM ACMIttIS~RATI0tt
~
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3.1 The Supervisor of Training and his staff are. respcasible for:
~ 'l %y.. c._..m Assigning instructors 'for the}CR lecture seriesD.4:,.
....r.....,.
a.
- ..g.
?
- .,., M.
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x Cetemining _:R assig.::ents for individual op n;v.,.
2.
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Maintaining and revieUno'ali records.
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j 4.
Assigning der,iciencies, detamining apprcpriate action to t
i clear deficiencies and clearing deficiencies upcn satisfactory i
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l ccmoletien of assigned action.
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, =
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- -Revision Z -.
04/11/77
~
5.
- Arranging accelerated iequalificaticn programs as mas be f-
- 1:'
necessary.
6.
Defining oral evaluation procedures.
7.
Scheduling necassary simulater time.
- ". >. ~
u, 8.
Prepare. license applications for lic'ense renewal. -
.x.
3.2 -The Supervisar of Operaticns, Supervisor of Training, or other..
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suitably. '
. x f.*
- . ray..,,..;g.cuSlifi.ed. person designated by the Unit Superint'ndant is' q../..C..
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Constructing annual written evaluation examinaticn, answers..
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19191072'
~PQS RO a SRO EXA!!IflATIO'l CATEGORY tlEIGHTIflG TA9LE
% OF TOTAL CATEGORY (RO)
EXAMINATION A.
PRIllCIPLES OF REACTOR OPERATI0ft 14 3
B.
FEATURES OF FACILITY DESIGil 15 3
C.
GEflERAL OPERATI?!G CHARACTERISTICS 13 : 3 D.
ItiSTRUffEtlTS AND CO?lTROLS 16 3
E.
SAFETY At!D E!!ERGEtlCY SYSTE?is 15 3
F.
STANDARD AtlD EftERGEllCY OPERATIllG PROCEDURES 16 3
G.
RADIATIO.'l CO.'iTROL A?ID SAFETY 11 3
% OF TOTAL CATEGORY (SRO)
EXAMINATION h.
REACTOR THEORY
]
I.
RADI0ACTI'/E MATERIALS HA? IDLING, DISPOSAL
& HAZARDS ALL '.lEIGHTED J.
SPECIFIC OPERATING CHARACTERISTICS EQUALLY (20",)
K.
Ti1EL HANDLIllG AtlD CORE PARAMETERS L.
ACMIflISTRATIVE PROCEDURES, CO.'lDITIO?ls AND LIMITATIC?iS
%N ggo 4 0W.
m en m,
REQUAL E Al'. II3til.TS 1 $ POST-0RAL I
linit !! RO i
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TOTALi REQ'D.
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.i i t.elitei'! Jp'll Categorfhs3 00!f i
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A
- Congra tula tio
- f i)-
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i-
)APPEtIDIXE l
m.
RO & SRO RETRAINING PROGRAM A.
PROGRAli AUDIT Station THREE tiILE ISLAt:0 Auditor F. KELLY Oate 5/3 a 5/a/79 UNIT #2 I.
Lecture Procram Subject Lectures Precared Reactor Theory
/
a Plant Operating e
Characteristics e I&C Systems
/
e Plant Protection e Procedures o RP e Tech. Specs.
s 10CFR, Ch. 1 II. OJT P1 ant M
Maniculations Cate NPPTS Data II ft/A 20 Hours S/6-10/77
!2 N/A 40 Hours 3/2C-31/78 SR3 il N/A 20 Heurs 1/2-6/79 12 ti/A 20 Hours 7/4-8/77
!3 N/A 20 Hours 2/5-9/79 44 N/A 20 Hours
.1/15-1?/79 APPENDiv F P'73 I 1919 075
III. Desien License & Oceratine Procedure Chances (Based upon most recent change)
Desien - See Below License See Below Procedure - SOP change review; Cycle 5-2 Desien License Procedurs W
0 W
0 W
0
_R0 fl OK Documentation for Cocumentation for
- 2 sign-off in Unit sign-off in Unit OK
- 2 C.R. OK.
- 2 C.R. OX
- 3 OK
- SRO fl OX
- 2 Same as Above Same as A50ve OK
!3 OK IV. Review of Contents of Abnormal /Emercency Procedures
_R0 SRO
- 1 - OX; 11/2/78 II - OX; 10/25/73
- 2 - OK; 10/5/78
- 2 - OK; 10/5/73
- 3 - OX; 10/19/78 s
f4 - OX; 10/12/78 V.
Cbservation 1 Evaluation cf Perfor ance & Cc cetency
- R_0, Da te SRO Cate 0
il 1/10/79 il 2/22/79 1919 076 12 2/3/79
- 2' 2/3/79 32 3/14/79 14 1/10/7?
APPE:;0:X F Page 2
R0 & SRO RETRAINIrlG PROGRAM B.
RECORDS AUDIT Station ruoer ni e tqt 340 Auditor F. RELLY Date 5/3 and 4/79 UNIT #2 1.
Written Examinations - Annual Remedial A.
RC[
Exam Date Grade Trainina
- 1 2/16/79 91.8%
None Required
- 2 2/14/79 87.4%
Yes - Cat. "0" Remedial B.
520 Exam Cate Grade Trainine
- 1 2/15/79 82.0%
Yes - Cat. (A,H);
0; E; & (G I)
!2 2/14/79 89.1%
None Required
- 3 2/15/79 93.0%
?'ane.Requi red
- 4 2/16/79 95.87
?!cne Required II. Written Examinations - Remedial Exam Cate Grade Action h?
Not yet administered SRO di Not yet administered 1919 077 ADPC' DIX F Page 3
_E i... 7., - 1.,..
METROPOUTAN EDISON C O M P A N Y se, o, c.=a,,s wo.- uw.., cmo,x.o,,
0 L
T:!I :Tuclear Station l
S.:h,ie :
U:IIT I/II REQUAL PROGP.At: ATTE::DA:: I Location !!iddletown, Pa.
To c, p. MILLER
- 1. J. P,055 J. P. O' HAULO:I W. J. lMRS:-3.LL G. A. ::U:: DER C. L. GL73RII J. R. FLOYD K. P. BRYi. !
J.
_s.
- c. n. L..
S.dIFT SU2.:o.n..s-n..>.-a
..a U,.I-1 I5.--
C.3..4 L.,, A 4, II 2n :;
dA:i c. tr.
--3.;,rJs A
- v.
The third 5-week requal training cycle was completed en August 20, 1979.
The training records show an everall attendance of 55*3 for all licensed personnel during this pericd. These figures are hroken dcwn as follcas:
GROUP ATTEfDAliCI (%)
2nd 5-week 3rd 5-week Cross License 20 27.5 Off Shife Persennel 29 Unit I SF.0 20 22 Unit.I CR0 63 45 Uni II SRO 33 44 Unit II CRO 50 85 The above figu as shcw a ver-f slight impr:.e=ent," but overall approximately half the licensed people are not at ending requal training.
The present requal cycle in prog-ess centains important training, especia11f for the Unit I persennel. Standard Tech. Specs. (Unit I) and First Aid Training a e both being taught 1:'is cycle. The implementatien of STS ic approaching rapidly.
As shcun by the attendance figures, the Unit I SRO and Cross-License per-sonnel are lcwest in attendance. These pe:ple cust knew the Tech. S;iacs.
First Aid Training is a required training by HFP 1570.9.
This is a diffi-dult portion of raining to makeup cr reschedule. Please try to attend.
Cue to excellent c operation between Safe-/, Operations and Training, ever r-one met the Fire Fighting Training requirement. This shows it can be done.
2 0 0 a u - a _.
1919 078 M. L. Beerc e,,
..vo,
- ' f 3,/.4 v. -
. 3 CL o.
.i. Icch:3.n C. J. Tr:ffer Apce'DIY e, P319 I 1...-
.. c. 5 -- 0. c, 10....... c.,....3 u.
..am
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^
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)
METROPOLITAN EDISON COMP A N Y w e,v a cc-:..
rac uso, co,r,x o,,
TMI !!uclear Station Lee:: ion tiiddletown, Pa.
subject UillT I/II REQUAL PROGPAI! AT~E!!DAi:CE Date tovember 2, 1978 To G. P. tilLLER ti. J. ROSS J. P. O'HAi:L0tt H. J. MARSHALL G. A. KU: DER R. S. HttTCHII:50i!
i J. R. FLOYD K. ?. BRYAll J. L. SEELI;:GER SHIFT SUPERVISORS I
SIIIFT FOREMEfL P
i I
The fifth 5-ueek training cycle was completed on October 27, 1978. The training l
records show an overall attendance of 36:', for all licensed personnel during this I
period. These figures are broken down as follows:
Attendance M) t-Grouc Dual License 30 Off-Shif t Personnel 30 Unit I SR0 47 Unit I CR0 57 Unit II SR0 33 Unit II CR0 44 The above figures shcw a decrease in attendance from the last report.
[
The present requal cycle contains dealth Physics Recertificatien, Fuel Handling Training, idath Review, Reactivity Balance Review as well as other worthwhile c
training.
l The Requalification Exam and Orals follcued closely by Unit I refueling are fast
}
approaching. The requal cycle which starts on December 4, 1978 will contain review classes for the Requal Exam.
i
-O
[.A' el 22 S. -
M. L. Seers -
Group Supervisor - Training T
l1LS/drg f
cc:
R. U. Zechman g g Qf 9' G. J. Trof fer 1
1 I
- Poet'0!Y G
'-go 2 Di
!?!T 2 R -O F :!C'd " E " 3 0..'. T! D U T.*
i
TM79-31 METROPOLITAN EDISON C O M E A N Y cesa,y o, c,,,,, m.m uwmo co,no, won TMI f:uclear Station subiser UNIT II REQUAL PROGRAM ATTE;!DAllCE Lcca:ica Middletown, Pa.
c bruary 16, 1979 Oste e
To J. L. SEELIi;GER J. B. LOGAM The first 5-shift training cycle of 1979 '.tas cc pleted en Feb. 9,1979.,
The following classes were taught and those licensed personnel not in attendance are listed for each. class.
Caring this pericd of time Unit I personnel and Shift Supervisors were attend-ing siculator training at the B&W simulator.
Systen Trainino - SSC'.1, SSR!i D. I. Olson J. L. Seelinger J. R. Floyd L. O. Wright K. R. Hoyt W. J. tiarshall M. S. Colecan R. R. Bcoher R. S. Hutchinson J. B. Legan H. W. Hartman M. J. Ross A. U. Miller Administrative Procedure Review 1001 A. W. fliller J. B. Logan K. 3. Hoyt W. J. !!arshall J. R. Floyd M. J. Ross R. S. Hutchison J. L. Seelinger Security System Modification A. U. f tiller J. B. Logan K. R. Hoyt
'1. J. fiarshall J. R. Floyd fi. J. Ross R. S. Hutchison J. L. Seelinger Ucrk Recuest Procedure Review 1407-1 A. U. itiller J. B. Logan K. R. Hoyt W. J. ftarshall J. R. Floyd M. J. Rcss R. S. Hutchison J. L. Seelincer 1919 080
~
fl.E.T.Uater and Haste Treatment A. U. !! iller J. B. Logan J. R. Ficyd R. S. Hutchison W. J. tiarshall M. J. Ross J. L. Seelinger u n m/.x.I h -
M. L. Seers Grcup Supervisor - Training cc:
G. P. itiller, M. J. Ross,
'p'ge,,x 3 pa=g 3 J. R. Floyd, File
"~
~
1 C9-O F FICE '2E. g;,,c u,1
g 5
Proc. No.
Op-3106 Dept. Supv.
~@
Rev. No.
10 Plant Supt.
/Ms Review Date 12/80 LOSS OF t!AIN CCOLUT SCOPE To prescribe the actions to be taken by plant personnel in the event of a loss of t!ain Coolant Accident.
~.
INCLCSURES OP-3106 - Pgs. 1 Rev. 10 g
0FF-3106.1 &.2 - Rev. 10 REFERENCES
)
1.
MES me=o 196/72, Yankee-operation of ECCS Ao'ril 3',197 (Tech.
File C-8,1972)
/ /'
/
/
2.
Proposed Change 145, Supplements 2-5 and Supplemen, 5 Error
/'
to and Corrections 3.
Approved Changa 97, Supplement 3, Attachment, ll i
4.
MES Mc=o 181/72, Operating Philosophy of YR Hydrogen Control
/
27,1972 (Tech. File C-19, /1972)
System, March 5.
Proposed Change No. 117, Supplement 3 n elosure A
/
r 6.
SEG Memo 271/78, "YR LOCA Procedure'?, November 23,' 1973 l
- /
7.
SEG Memo 159/77, " Operation o: YR.ECCS", Dec. 5. 1977
'/
/
DISCUSSION
~.Q
/,,..
A loss of coolant accident'if defR.ed as a breach of the reactor coolant system boundary which refults in the interruption of the normal mechanism for removing f; eat from the reactor core and exceeds the available capacity of ths' charging system.
The primary system pressure decreases.
'a~nen the main coolant system pressure has decreased to 1700 psig or the vapor contai:
pressure
.has increased to 5 psig, automatic initiation of the emer;ency core cooling system occurs to cool the core and prever.t fuel meltdown.
t-i 1919'081 APocNDIX 4 Page I
Rev. 10
.. r Boron concentrations, foiloving a cold leg bresk, will begin-to increase within the cort. region due to steaming in the resctor vessel.
It is determined that the solubility limit of 47,000 ppm at 212F vill be attained during the recirculation phase of long ter:n cooling unless water can be forced to circulate through the core region.
T'.arefore, hot leg injection will be started prior to reaching the solubility limit for boron in the core region. [5]
The accident snslyses for cach si = break assumes a power level of 618 MWt immediately prior to the bresk. [2]
While in Mode 3 between 1000 psig and 1800 psig safetf injection must be manually initiated. Obviously, the decay hest in this range is much lower than during power operation, especially if the reactor has been shutdown for several days.
Consequently, the actions required in this situstion will differ and are noted as applicable in the procedure.
.,\\
C If a loss of main coolant occured while in Modes 4, 5 or 6( rather than follow this procedure, the primary concern of the operster is N to keep the reactor core ficoded and cooled.
,'.1,-
'. [,)
- SYMPTCMS
/
1.
Main coolant low pressure alarm, reactor scram and turbine tT,ip.
//
2.
Charging flow increase and standby pumps auto start.'durin,, the initial phases of the accident.
/
/-
^
/
p, a.
3.
Pressurirer low level alarm.
\\,
/
Main coolant low flow trip and alarm'as M.C. pupp cavitate 4.
because of pressure reduction.
/
/
5.
Rsdistion monitor alarm initiated by, one.o.r'both of the vspor container air particulate monitors..' /
/
6.
Vapor container high pressure al'ar:4 2.5 psig.
- l/
- +
/
AUTOMATIC ACTIONS [ *. 's
- 4(%' j/
..V 1.
Resctor sera adturkhetri' when pressure drops to 1800 psig.
N/A Mode 3.
T 2.
Safety Injection Syst.m utomatic initistion as. primary pressure drops to 17.00 psig sad or V.C. pressure reaches 5 psig. N/A Mode 3.
- 3. [t *harging pump r.cip on safety injection initistion.
i919 08'2 8
APPC'!O!X '4 Page 2
DRILL EVALUATION SHEET DRILL:
Reactor All Rod Scram Crew:
Date:
Cperator Rescense:
1)
Verify autcmatic actions occurred 2)
Insure water level being maintained.
If not, insure at least one (1) CCCS pump operating 3)
At 2 to 3 MWe, open 25 N31 and switch Regulex to " Manual", trip turbine 4)
Maintain reactor pressure with MS3V as needed 5)
Bypass keys 17 and 13 to normal 6)
Turn High Voltage on for Source Range Chanr.als 1 and 2
~
7)
Downscale Wide Range Channels to monitor reactor pcwer level The above is the irrediate action required by the Energency Precedure for an all rod scram.
Evaluation will consist of satisfactory or un-satisfactory indicaticn in each step of the observed or discussed response.
I
?2MA?25:
e.
f919 083 i
l Conducred by 6
4 A ? o c>'0 ! Y I Page 1
N*
t SIMULATED CONDITIONS FOR DRILL There are many conditicas which could lead to the use of the all red scram procedure.
It is up to the evaluation to deter-mine cause and for the scram and make appropriate cctments in the remarks section of the evaluation sheet.
Examples of conditions to be simulated are:
1)
Less of Reactor Feed Pump 2)
Loss es Condenser Vacuum 3i Manual Scram 4)
Less of voltage en Reacto: MCC 1A 5)
Power / Flow Abnormal 6)
Ei Flux scram 7)
IPR Failure.
i91<) 084 e
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3