ML20090J799
| ML20090J799 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/23/1992 |
| From: | Hampton J DUKE POWER CO. |
| To: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML15239A055 | List: |
| References | |
| NUDOCS 9203180049 | |
| Download: ML20090J799 (70) | |
Text
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ENCLOSURE __3 puht 1%ti Company (MD M2 SM tkone e Nudrat Matu>v l'O flux I4M knet;t S C :nT4 DUKE POWER January 23, 1992 i
Mr. Thomas Pooblot.
Operating Licensing Section U.
S. Nuclear Regulatory Commission Suito 2900 101 Mariot.ta Street Atlanta, GA 30323 Subjects Oconee Nuclear Station Facility Comments on RO and SRO License Written Examinations Given Jar.uary 20, 1992 Doar Mr. Poobles:
1)
Facility Comments
- 26 RO Exam.
Thoro is ao correct an'mor because the EOP conflict.s with the AP, allowing up to thirty (30) minutos of LPI pump operation with minittom recirculation (i.e. loss than 800 gpm).
Facility Justification Hofer to EOP Sect. ion 505, Pago 4 attached.
" Operation of the LPI pumps against a hhutoff head must not exceed thirty (30) minutos or overheating and pump clamage may result. "
Student foodback following the written exam generat.ed this comment.
2)
Facility Comment:
- 32 RO Exam and #33 SHO Exam.
The correct aaswer to part "c" is "10".
(Can be manually operated to control ficw.)
Facility Justificationt Refor to Loss of 1FI Bus, AP/1/A/1700/23, Page 1 attached.
"111P-120 (RC Volume Control) swaps to 1KU and is manually operable."
Thoroforo, the correct answer for part "c" is "10" in Column B.
The Answer Key used in t.ho pre-exam review was correct, llowever, a typographical error sooms to have occurrod once the Answer Key appeared in its final form.
3)
Facility Consent.
Thoro art no correct answers for thia question.
Tho question should be doloted froni the exam.
(continued) 9203100049 920303 gDR ADOCK 03000269 PDR b
Pago 790 January 23, 1992 3)
Facility Justification:
Por the attached AP and OEE, IRC-66 closes on loss of K1 power and can be opened from the switch in the control room.
This question was rewritton during the pre-exam review.
Utility comments are missing from contractor's packago.
4)
Facility Comment Question #39 RO exam and question #40 SRO oxam. In addition to choico "b" being correct, choico "d"
la also correct.
Facility Justification:
Verifying that tho water box omorgency discharge valvos are open ja also one of the Immodlato Manual Actions in AP/1/A/1700/13 caso B.
Refer to attached copy of the Abnormal Procedure noction.
This mistake was not detected during_the pro-exam review.
Facility clarification comments were factored into choico "b".
5)
Facility Comment
The correct answer should be "d".
Facility Justification:
As por Station Directive 3.3.1, Pago 2 (attached), refer to Section 3.15.2 which states that with completed NHC Form 4, the administrative wholo body dose limit in 2500 mRom in any calendar quartor, or 5000 mrem in any calendar year.
Since the given whole body doso is 100 mRom to dato, the individual can still rocoivo up to 2400 mrem maximum dose with a doso extension.
Thorofore,=the correct answer is "d".
This was discussed during the pro-exam review.
The changes which the f acility requested were raado.
However, the Answer Key was not changed to "d",
as it should have boon.
6)
Facility Comment
- 46 SRO Exam.
None of the choices given are correct.
Choico "d" would be correct only if stated as follows:
" Installation and removal of supplemental red tags on compononts with station rod tags,"
Student feo3back following the w -tton exam gonorated this comment.
Facility Justification:
Refer to attached Station Directivo 3.1.1,.Pago 3 of 23, Section 4.6.3.
"The work group shall not
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place supplomontal rod te;gs on any. station equipment that does I
not prosently have at least one station two part serialized red tag (ntub type) attr.chod".
(continued) i e
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ww Pago Throo January 23, 1992 7)
Facility Comment:
SRO Exam #47.
Choices "b" and "n" aro Correct.
Facility Justification:
Choico "c" is also correct becauso
" block tagout" con bo interpretod as equipment isolation.
Suo attached Station Directivo 3.2.1, Pago 15, Section 6.9.1.
Refor to "clearanco to begin work means: (1) Any equipment isolation required to perform the requested work havo Loun mado".
Student foodback following the writton exam generated this comment.
8)
Facility Comment:
Choices "a",
"b" and "c" are all correct.
Facility Justification:
Refor to attached Station Directive 4.1.3.,
Page 13, Section 4.5.1.2B.
Choico "b" can be interproted to fit the employco responsibility B7, " observing recommended stay times".
Choico "c" can be interpreted to fit 11 6, " Working at a doliberato pace rather than rushing or overextending themselvos."
Thorofore, choices "a",
"b" and "c"
should be considered acceptablo.
Additional references were roquested for this question during the pre-exam review.
9)
Facility Commentt
- 53 RO Exam, choico "c" would be correct if ACD-4 were shut instead of ACB-3.
Thorofore, both choices "b"
and "c" shoulci be considered correct.
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Facility Justification:
Refer to attached handout drawing of the Keowoo Electrical System, OC-SPS-KHG-20.
F1ca' path for energizing CT4 underground feeder from F.oowee Unit 62 via ACB-4 is highlighted on the drawiny.
This correction was not mado during the pre-exam review.
I 10)
Facility Comments:
455 RO Exam and #61 S30 Exam.
In addition to choico "d" being correct, choico "h" should also be considered' correct.
Facility Justification:
Choico "b" should also be considered correct since the MS Line'Rollof Valves open at various sotpoints, ranging from 1104 psig to 1050 psig.
The relief valvo opening timos may vary by milliseconds following a Turbino trip from 100% power, but it will.be sequential.
On the other hand, to the casual observor, choico "d" would appear to be correct.
Therefore, both answers should-be considered acceptable.
Hofer to attached pago 8 from MS Lesson Plan and attachod copy of OFD 122A-1.
Student feedback following the written exam generated this comment.
Page Four January 23, 1992 11)
Facility Comment.
Choices "a" and "c" should be acceptable.
Facility Justification:
The student is required to know the minimum flow but not the maximum flow, per the Reactor Building Spray Lecson Plan, OP-OC-PNS-BS, Objective B2.
The applicable KA number 026000K6.02 threshold is 2.4 (i.e. less than 3.0).
This was idiantified during tne pre-test review as unnecessary memorization of numbers.
Refer to Lttached RO and SRO 'Irajning Objectives, for BS System.
12)
Facility Comment:
Insufficient information was provided to indicate that RCS pressure in increasing, due to a high concentration of noncondensable gases in the pressurizer.
Therefore, the question should bc deleted.
Facility Justification:
The initial conditions of the question should hnve stated that pressurizar level was increasing A pressurizer level increase with noncendensable gases woula have resulted in increasing RCS pressure as the nonconderlable gases were compressed.
This was not discussed during ti.e pre-exam review.
Another correction was made to this question during the pre-exam review.
13)
Facility Comment:
- 86 SRO exam.
For "b",
either choice "3"
or "4"
is correct.
Also, Column B #6 should read "Provides" lastead of "P rotects~'.
This mietake In the wording of Column B#6 invalidated it as a possible correct answer because it did not make sense.
Student feedback fellowing.the written exam generated this cornment.
Facility Justification:
Refer to RFS Lesson Plan, Page 21 attached.
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14)
Facility Comment:
Correct answer should be "a".
Facility Justification:
The students were not provided with the updated Lesson Plan revision of October, 1991.
Lesson plans sent to the NRC were copied and mailed Jn November, 1991.
Therefore, the students' original nandeuts prompted them to select choice "a" es a correct answer.
Refer to attached page 10 of :.evj e ton 04, dated 04/29/91, to Prncei.:s Radiation Monitor Lesson Plan, OP-OC-WE-PRM.
(continued) e
i Page Five January 23, 1992 15)
Facility Comment:
RO Fxam questions 49, #26, #27, #31, #39,
- 42, #43, #44, #45, # C.
it7, #48.
These questions are inappropriate on the eu ex am because related refarences were not providad wJth th<
"O examination.
For the SRO Examt questions wo,
, 7), #32, #40, #43, #44, #45, #46, #47, #48,
- 49, #50, #51, #52, 153, #54 are inappropriate because related references were not provided with the SRO examination.
d 9
Fr.cility Justification:
Accordi.g to ONS Training Objectives, a copy of Station Directives is provided during examinations.
Refer to attached LRO and LSO Training Objectives for the Station Directives Lesson Plan, OP-OC-ADM-SD.
Furthermore, according to our Shift Review Guide Lesson Plan Objectives, students are allowed to. refer to appropriate AP's and OMP's, with the exception of items in OMP 2-1, (attached) which must ba. memorized by the student, in accordance with Operation's Management Philosophy..
The depth of the questions required on A!'s and Staticn Directives in the RO and SRO exam was anfair without providing related references.
liefer to attached copy of shift Review Guide LRC and LSO objectiven.
During the pre-exam review, the facility-Training and Operations representatives repeatedly commented that additional references should be provided for Station Directives and Abnormal Procedure questions.
We appreciate your prompt attention to these matters, sincercly, 4 /h 6
J.W. Hamhton, Vice President' Oconee Site xc:
Richard Baldwin, Chief Examiner H.B. Barron, Station Manager /ONS G.A. Ridgeway, Shift Operations Manager /ONS.
P.M. Stovall, Director,-Operator Training /ONS R.L. Sweigart, Superintendent of Operations /ONS L.V. Wilkie, Training Manager /DNS JWH:TLF:ks 4
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Un!t 1 Page 4 of S.
EMERGENCY OPERATING PROCEDURE EP/1/A/1800/31
.Sttc_ tion _1QE ER_A.cluatian 2.0 1E RCS pressure 1 550 psig.
THEN verify ES channels 3 and 4 actuated:
All ELua ES module " AUTO" lights on All--White ES module " POSITION"' lights on 2.1 Verify CFTs dumping.
CA2TlpQH 12. 2 J operation s of l'- the V LP I ? pumps 9 aga ins t:L a i shuto f f a head..: mus t.
not% exceed : 30 minutem s;or/ overheating? ands pumpgdemager
- 3 may;resultk s
4 2.2 Limit LPI Headar flow-to 5 3000 gpm/ pump.
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$53 500 CVMW7 Unit 1 Page 1 of 17 OCONEE NUCIEAR STATION LOSS OF IKI BUS AP/1/A/1700/23 1.0 Lurpose This procedure provides the actions necessary to maintain the plant in a safe condition following a partial or total loss of power to the ICS and Control Room Indications.
2.0 Spptoms "EL.1CS INVERTER SYSTEM TROUBLE" statalarm (1SA-6, C-2)
"ICS MAN POWER FAILURE" statalarm, (ISA-2,.B-12)
"lCS AUTO POWER FAILURE" statalarm, (ISA-2, B 11)
"!CS EMER POWER FAILURE" statalarm, (ISA 2, E 11)
"ICS EMEliG F.W. POWER FAILURE" statalarm, (ISA-2, D-11)
Other numerour, alarms as instruments fall All Bailey Hand / Auto Stations may lose indicator lights.
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l 3.0 Automatic Systemr Actions l
Main FDW pumps trip l:
Reactcr trip Turbine generator trip M operable EFbWPs start ll 1HP-31 (RCP Seal Flow Control) swaps to 1KU and controls at setpoint
.1HP-120 (RC Volume Control)"swapsW1KUrand is manuallyc perable j
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IHP-7 (Letdown Control) swaps to '1KU and is manually operable.
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Unit 1 pfg6
- 3 7 SMo LOSS OF 1KI BUS AP/1/A/1700/23 ENCLOSURE 6.2 Guidelines For ICS Auto Power Failure 1
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.0 IF ICS Auto Power failure has occurred, THEN perform the fo' dowing to recover ICS Auto Power'.
1.1 Verify the breaker for Auto Power i'1 the back of ICS Cabinet #4 "ON."
1.2 Verify breaker #25 (ICS Auto Power) in 1KI Power Panelb 1 d "ON. "
2.0 The following equipment should be operable for the conditions noted:
PZR Heater Bank Two, operable from the Aux Shutdown Panel I
1RC-1 (PZR Spray), operable with no position indication from UB1 and from keyswitch in ICS cabinet #13 1RC-3 (Spray Block), operable with no position indication from UB1 1HP-7 (Letdown Control), manually operable witi1 no flow'
+
indication 1RC-66 (PORV), operable from the Control Room switch.
3.0 The following Bailey Stations are manually operable, (auto function and light indication are lost):
Turbine Bypass Loop A and B
+
Steam Generator-Reatar Steam Generator Load Ratio Reactor Demand Loop A and B FDW Demand Loop A and B Main FDW Valves Loop A and B SU FDW Valves.
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0-711-E C/D IUS2-AND TE26 6 & 7 CLOSES AC3vE 2276 PS! RC PREc h 4711-G C/D 1082
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M-201-627' B 1 W ELEMENTARY DIAGRAM OH-201-591
-- DRESSER VALVE OUTLINE B/M 0-720-A BILL 0F HATERIAL D8032332C 0 - 711- 0 2 O/L IU82 0-7t t- 02.01 COMP. INDEX,1082 LEGEPO
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Unit l' 4
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_ {[h -gpfg/7M Page 7 of 15 LOSS OF CONDENSER CIRCULATING WATER INTAKE CANAL / DAM FAILURE AP/1/A/1700/13 CASE B Dam Failure Without Loss Of CCW Intake Canal Immediate Manual Actions 4.0 Immediate Manual Actions CAUTION The: amount of inventory loss from the Intake
- Canal is directly related to the amount of time that elapses during the_ completion of~this Section.
_4.1 Monitor lake level for indict. tion of dam-failure:
4.1.1 JF a dam failure hastoccurred,-
THEN manually trip-_the Reactor:
REFER TO EP/1/A/1800/01,.-
EMERGENCY _ OPERATING PROCEDURE.:
-_4,.2y; Depress.the"CCWDAM:, FAILURE"{pushbutton.
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Unit 1 Page 8 of 15 LOSS OF CCNDENSER CIRCULATING WATER INTAKE CANAL / DAM FAILURE AP/1/A/1700/13 CASE B Dam Failure Without Loss Of CCW Intake Canal Immediate Manual Actions 4.3 Verify;the.foll-owing:-
All CCW pumps tripped lCCW-1-6--(Waterbox Emer.Disch) valves openo All Condenser Outlet valves closed by computer point:
,1CCW-20 (Condenser 'lAl' Outlet)
D0273 1CCW-21 (Condenser '1A2' Outlet)
D0275 1CCW-22 (Condenser '1B1' Outlet)
D0277 1CCW-23 (Condenser '1B2' Outlet)
D0279 1CCW-24 (Condenser '1C1' Outlet)
D0281 l
1CCW-25 (Condenser '1C2' Outlet).
D0283.
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__4.4 Verify CCW-8 (Emer CCW Disch to Tailrace) opens.
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4.5 Verify at least one CCW pump discharge valve closed.
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l 4.6 IF all CCW pump dischaLJe valves'are open, l
THEN close the CCW pump discharge valves.
1 4.6.1 Press "CIOSE 1" and "CLOSE 2" on the "TURB BLDG FLOOD EMER CLOSING ALL CCWP DISCH VALVES" control switches.
4.6.2 After all CCW pump discharge valves are closed, press "OFF" on both switches.
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o Unit 1 Page 9 of 15 LOSS OF CONDENSER CIRCULATING WATER INTAKE CANAL / DAM FAILURE AP/1/A,1700/13 CASE _a
_D_atn F ailure Without_ Loss Of_C&W_I_atake Canal immedialt Manitall_clinna
__ __ 4.7 start the CCW pump with the closed discharge valve:
Verify the CCW pump discharge valve opens.
4.8 Verify the follnwing:
CCW-8 (Emer CCW Disch to Tailrace) closed Discharge valves on tripped CCW pumps closed CCW-9 (Emer CCW Disch to Intake).open, 4.9 II CCW-9 (Emer CCW Disch to Intake) does NOT open.
IHEN send an operator to 'open CCW-9 l
(Emer CCW Disch to Intake):
Noti fy _ security that access to CCW-9 (Emer CCW Disch to Intake) is required, and to meet an nperator at the "IRW" Gate".
(Located at the Southwest earnar, inside the protected area.)
Obtnin the "CCW-9 IRW Gate" key from l
the security box in Unit 3 shift Suparvisor's office.
With security proceed between the fences to CCW-9.
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. SD 3,3.1 (TS)
NOTE: Completion of an EDC transaction or a dose card means that the individual has read and understood each RWP and has complied with its requirements.
3.10 Exposure shall be recorded en the DETRC in increments of 5 mR.
3.11 Information used in the completion of forms shal', he the-most current svailable on the Radiation ~xposure Control (REC) daily report.
3.12 R-cord time entries on the DETRC in military time (0000-2400 hrs.)
3.13 Any extension granted shall be valid only for the specific Job / task and period of tima for which it was granted.
NOTE: Under no circumstances is an extension granted at one station valid at another.
3.14 Non-licansee individuals shall provide a letter from their employer that ives permission to extend their dose to a given amount if either of the ollowing is true
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1) exposure limits set by Duke Power Company exceed limits set by tle individual's employer.
2) individual's accumulated exposure is 1000 MREM (or higher; or is expected to go above 1000 MREM for the quarter.
3.15 No licensee or non-licensee emp.loyee shall-be allowed to receive a whole body dose equivalent that exceeds:
3.15.1 without completed NRC4:
1000 MREM in any calendar quarter or 4000 mPIM in any calencar year.
3.15.2 with completed NRC46*
2500 =,'nREM - in - any: calendar quarteri orz 5000 MREM Lin t any calendar,yeare 3.16 Internal exposure will be administratively controlled to 35 MPC-hrs in any seven (7) consecutive days.
3.17 Inaccurate EDC transcctions c erroneous dose cards shall be corrected to maintain accurate REC records.
3.17.1 Information used to correct inaccurate EDC transactions or errineous dose cards shall be provided by ths andividual-radiation worker-or the individual's supervisor.
3.17.2 After notification-vf an inaccurate EDC trancaction or erroneous dese card is made to the individual's superviror, a
-no forfeiture period of up to aoon (1200 hrs.) of the second working doy will-be permitted for an individual or supervisor to correct the problem.
3.17.3 If the problem with the inaccurate. EDC transaction or - rhe e rror.eous dose card has not been - corrected within the no forfsiture period, the dosimatry set assigned to' the radiation worker will be confiscated.
3.17.4 To release the confiscated t;osimetry set, the radiation worker's Section Manager or equivalent must contact the Radiation Protection hnager or designee and provide an understanding that minimized.
- errors in radtological records will be
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q Page 3 of 23 kQ hJy A0{&V 4.4 Lock-out 4.4.1 A device used to lockout the source of power at the main disconnect switch pr.ior to commencing work on or close to the machine or equipment.
4.5 Block Tagout A block tagout is the isolation and tagging of a defined portion of the plant for the purpose of allowing werk by various werk groups to be accomplisLed concurrently withir.the boundary of the block tagout.
4.6 Supplemental Tagging Departments or grotips that assign a coordinator to take responsibility for a BLOCK Tagout may require that individual to implement his responsibilities as defined
,j in 6.7.2 by use of a supplemental safety tagging procedure (i.e., Transmission Department Supplemental 4
Safety Tagging Procedure). This feature allows for more effective tagouts. Coordinators holding stubs from the operationally responsible group are rnst familiar with the scope of work and responsibilities of individual foremen and supervisors working within the boundaries.
It is the coordinators' responsibility to administer the suppli antal tagging procedure per the following guidelines:
1 4.6.1 The procedure is to be used primarily during unit outages and emergency situations when station manpower is short. However, it may be used anytime when more than one foreman or group is working on the same piece of equipment.
4.6.2 The work group shall not remove from, or return to service, any station equipment as this is the responsibility of station personnel assigned operr.tional responsibility.
4.6.3 The : work - group shall not" place suppit. mental red:tagsron any--station < equipment that-does not presently' hive"at^1 cast"eneistation=two-
-part serialized red: tag'(stub type)-attached.-
4.6.4 When working on equipment tagged to them,-the work group shall not change.the' position of a valve, switch, cut out or remove valve from the line, etc., that has a station red tag attached to it.
Contact the shift supervisor or other responsible station personnel to remove red tags if it is necessary to operate equipment to verify repairs.
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jf 5 107 (15) representative or verbal as allowed in Paragraph 6.6.1, shall be checked in the appropriate blank, "YES".
If ANI inspection is not required, the appropriate "NO" block will be checked.
The job supervisor shall contact Q.A. or the ANI inspector directly prior to job start so the ANI inspector can be scheduled in for che inspection.
6.8 Cleanliness Zone - The appropriate cleanliness zone shall be established per Station Directive 4.3.2.
If the Cleanliness Zone requirements change after work has started, the Craft Supervisor will make the appropriate changes to 6.8 of the W.R.
and take the appropriate actions per S.D.
4.3.2 to ensure conformity with the directive.
6.9 Clearance - The group ultimately responsible for the equipment to be worked on will be responsible for giving clearances / approvals to begin work.
The person filling out section II of Work Request shall indiccte in the clearanco block who is responsible, (i.e., OPS, HP, Chem., ENV., etc.)
for that particular area of work.
6.,9.1 Clearance to begin work shall be obtained from Oparations Supervisor (SRO') or tha responsible representatives as designated by the responsible group superintendent, who has control over the structure, system, or component.
l If work is delayed (not started in a reasonable amount of time - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), Reclear.tnce is needed to begin the work.
The job supervisor shall stamp the work request in Section V with a stamp which reads "Reclearance To Begin Work Bys" and the l
date.
l Reclearance is not required on equipment which the Work Supervisor /Coordiaator controls by red tags.
Reclearance to start work shall be documented by this signature and date.
Clearance to begin work means:
(1); Any equipmentLisolationfrequired=to-perform
'the requested' work 1have~been'made'.=
i (2L Verification-thatz limiting-conditions for Y
operationi are:not violated.
(3)
Post Maintenance Testing specified on the attached PMT Sheet can be performed at the completion of the maintenance planned.
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It is the responsibility of tbn Work Supervisor to file a briaf follow up report to the Safnty Unit after each high temperature job so that tha station can continually nvaluate the effectiveness of this program and make thn necessary adjustments based upon actual working experiences.
4.5.1.2 Esoleven A.
It is the responsibility of each worker assigned to work under hot conditions to adviso his supervisor and the Medical Unit if on any particular day for reasons'of health he does not feel that he or nhe is suited for such duty. Vorkers will not be required to work under extremn conditions if such a health problem exists.
B.
It is also the responsibility of each employee to practice common sense preventative measures in order to further rnduce the chances of veloping heat related disorders by:
1.
Boing awaro of the symptoms of -
heat strans.
2.
, Working-with n _ partner and observing each other, 3.
Drinking water or other fluids frequently.
4.
Keeping themselves in good phys ical condition.
-5.
Wearing 1(ght colored, loosn fitting, cotton clothing where possible.
6.
<Workingt atoa: deliberate pace
'rether than rushing' or over-extending themselven.
7.
- 0hservingorecommendedtstay-times.
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p h h/h h(2 Page 8 of 17 5.
Relief valve settings are staggered so that at a 100%
turbine load trip, all MSRV's will open, but resaat In a-pattern-designed so that as the heat generated by the primary drops, the number of valves remaining open decreases, until all relief valves are closed and OTSG pressure is being controlled by the TBV's.
- 6. These staggered settings, while-still protecting the lines from overpressure, also prevent excessive blowdown which would result in excess 1.ve cooldown of the primary.
7.
The relief valves are designed-for as much as 6%
blowdown, meaning that they may reseat as low as 94% of lift pressure.
This is accomplished by the use of a i
conical shaped valve-disc which offers _more surface area for the steam once it has opened.
This design is necessary so that the valve is not constantly " popping" and reseating at lift pressure.
- 8. With this in mind one can see that the 2 relief valves with the lowest lift settings (1050 psig) may not resent until pressures as low as 977 psig.
_(Byiprocedureithe/
acceptable;11:ftcsettingirange:forithef3_/ lowest valvesYis~
.1039:1060xpsig)
- 9. This is the cause for 2 (or more)' relief-valves remaining open at normal post trip steam pressures of ~ 1010 psig.
Operators should realize that this 1s somewhat expected i
and that it is incorrect to immediately assume that these relief-valves are " stuck"'open, which would indicate a mechanical-failure of_the valve (s)
- 10. The Trip Recovery procedure now addresses lowering staam header pressure in order to rescat MSRV's.
Also a station problem report has been submitted for this design deficiency.
Thus far, no changes have been made to the lift settings for the valves, howevercrelief valve maintenance during outages has been upgraded and the blowdown rings have been opened up somewhat which has helped reduce the blowdown of these valves.
- 11.. ork in and around the MSRV's while the unit is at power W
should never be allowed due to the potential for_a
. reactor trip and subsequent-lifting of the'MSRV's.
Serious personal injury could occur if entry were allowed in this area (steam burns or hearing loss).
Rev. 02/ll-ll-91/GCW
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Page 3 ci 16 hkI f
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LR0 - TRAINING OBJECTIVES jf
~
1 The student will:
TIME:
J_13our A.
Terminal Objective e
- 1. Describe the purpose, location, modes of operation, and precautions related to Tech. Specs. in regard to the RBS System.
The student should also know the ES setpoint and euuipment associated with this system, and recognize important power supplies.
B.
Enabling Objectives
- 1. State the three (3) purposes of the RBS System.
- 2. List the minimum flow requirement for the'RBS pumps.
q
- 3. List the power supplies for the following RBS System components:
a.
RBS pumps
'A' and
'B' b.
BS-1 and BS-2
- c. BS-3 and BS-t.-
4.
State the setpoint, statalarms armed, and equipment actuated by ES Channels 7 and 8.
5.
List t.he normal flow values for each RBS pump in both the ES mode and recirculation / piggyback mode.
- 6. Given a drawing or list of RBS componants, properly r.equence the RBS flowpath in each of the following modes-a.
Engineered Saft.;
- ds (ES) b.
Recirculation / Piggyback from RBES
?
- c. Recirculation to the BWST (testing)
- 7. Describe the Tech. Sper. precaution to be obse2.ved when running a RBS pump in the recit ulation mode for testing.
8.
Describo the purpose and the basic method to perform the functional test of the RBS Check Valves.
Rev. 03
/09-17-90/WRM
p a in #76 SRo a d
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f' 7 h l('
OP-OC-PNS-BS March 02, 1984 LMH/
Page 4 of 16
(
LSO - TRAINING OBJECTIVES The student will:
TIME:
1 Hour A.
_ Terminal Oblective 1, Describe the purpose, location, modes of operation, and precautions related to Tech. Specs. In regard to the RBS System.
The student should also know the ES setpoint and equipment associated with this system, and recognize-important power supplies.
B.
Enabling Obiectives
- 1. State the three (3) purposes of the RBS System.
2.c Inst a the-Minimum' flow e requirement *forothe.RSS pumps.
- 3. List the power supplies for the following RBS System components:
- a. RBS pumps
'A' and
'B' b.
BS-1 and BS-2
- c. BS-3 and BS-4 4.
State the setpoint, statalarrus armed, and equipment-actuated by ES Channels 7 and 8.
- 5. List the normal-flow values for each RBS pump in both the ES mode and recirculation / piggyback mode.
- 6. Given a drawing or list-of'RBS components, properly sequence _the RBS'flowputh in each of the following modes:-
3
- a. Engineered Safeguards-(ES)
- b. Recirculation / Piggyback from RBES Recirculation to the BWST (testing)~
c.
- 7. Describe the Tech. Spec. precaution-toLbe observed when running
(
a RBS pump in.the recirculation mode.for testing.
8.
Describe the purpose and the basic method to perform the functional test of-the RBS Check Valves.
Rev. 03~ -/09-17-90/WRM j
i_
_p f( _ h* O Eyde, OP-OC-IC-RPS V4Ts September 30, 1983 -LMH/:
Page 21 of 80 2.0 PRESENTATION 2.1 Protective Functions A.
High Flux Trip at s 105.5%
- 1. Technical Specifications requires high flux trip at no greater than 105.5%; Actual RPS set points are set at 104'.75% for conservatism.
- 2. The hign flux trip is provided to prevent damage to the 2uel clad from reactivity excursions too rapid to be detected by pressure or temperature measurements of the RPS.
- 3. The Tech _ Spec set point of 105.5%.is based on not excending the maximum power-levels reached in the1 Safety
-Analysis Reports; this value is nominally 114% of Full Power.
When 105.5% RPS set point is used, adding to-this the variations-that could result due to calibration and instrument errors _and the delay time from trip set-point reached until the power excursion is terminated,-the maximum power level reached could be 112% Full Power.
E. High flux trip-based on RCS Flow and Axial _ Imbalance.
~
(Flux / Flow / Imbalance)
- 1. Technical Specifications Maximum-Allowable _ trip set points for various combinations:of reactor power and RCS flow-cre shown in Handout OC-IC-RPS-5.
- 2. Specified power / flow set points _ prevent a DNBR of_less than_1.3 occurring should a loss of RCS flow-occur at high power. due to an electrical malfunction.-
- 3. Set points based on 100% design flow - since actual RCS flow is greater than design; flow'(- 107%-for Unit.1,2,&
- 3) this credit-for additional flow is~taken when establishing-trip set points based _on RCS-flow.
100% x 1.07 = 107%
(Unit 1,2,& 3).
- 5. With only 3 RCPn operating, design flow rate is 74.7%.
- 6. For 3 RCP combinations, the trip set point is derived by:
74.7% x 1.07 = 79.9% Full Power-(Unit 1,2,& 3).
Rev. 06/05-09-90/ JAW-I 1
V ~Q <) h4-) k $ f bh Q) i OP-OC-WE-PRM
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- 3. Detector sodium iodide.
- 4. Located at vent stack.
I. RIA-41 (1) (3)
- 1. Similar to RIA-39,
- 2. Monitor air in spent fuel pool.
- 3. Detector plastic beta.
4.
Suction entrance to spent fuel pool.
Located adjacent to CC Surge Tank J. RIA-42 (1) (3)
- 1. Monitor RCW return from auxiliary building.
- 2. Detector sodium locide.
- 3. Located in turbine building basement behind backwash pumps.
K. RIA-43, 44, 45 and 46 (1) (2) (3)
- 1. See Handout OC-WE-PRM-7.
- 2. Monitor Unit vent for radioactive air particulates, gas and lodine.
- 3. Located on skid in vent stack room.
- 4. RIA-43 plastic beta detector.
- 5. RIA-44 sodium iodide.
- 6. RIA-45 plastic beta.
7.
RIA-46 G. M.
- 8. RIAL 451 interlocked'tostopReact$ryBul'1dingPUrgelandf
^
ReactocBuilding; Mini 4 Purge' Fans'and= closet R.BMisolatilon valves-prs 2,N3c,m4 T 51 L. RIA-47, 48 49 and 49a (1) (2) (3) 1.
See Handout OC-WE-PRM-8.
- 2. Monitor reactor building for radioactive air particulates, gas and iodine.
Rev. 04 /04-29-91/JMB T
q) d'2, /;' / oJ y'
OP-OC-ADM-SD February 19, 1985 MDT/
Page 7 of 24 LRO TRAINING OBJECTIVES The student will be able to do the following:
SINE:
4 Hours
- Uj A. Terminal Objectives
- 1. Apply the appropriate Station Directive (s).to given situations, either using a copy of thu directive or from memory as required.
D.
Enabling Objectives:
- 1. Given a copy of Station Directive (S.D.)2.2.1, Station procedures: (R1) a.
State when a procedure change vould be deemed necessary,
- b. Determine the validity.of a procedure control copy check, c.
Determine if a procedure-must_ be in the user's possession prior to its performance.
- 2. Given a copy of S.D.
2.2.2, Independent Verification: (R2)
- a. Determine whether a given example is a proper method to identify a component's status,
- b. Determine whether or not inaependent verification is required for a given component or system.
- c. Apply the precautions listed in the directive to-given situations.
- 3. Select a correct method for independent verification, given several choices, in accordance with S.D.
2.2.2, Independent Verification. (R3) 4.
In reference to S.D.
3.1.1, Tagging: (R4)
- a. Identify those who are responsible for-issue and recall of Operations' tags,
- b. State the general purpose of red, white, and yellow tags.
Rev. 06 /10-15-91/GCW
-i OP-OC-ADM-SD February 19, 1985 MDT/
Page 8 of 24 LRO TRAINING OBJECTIVES
- 5. Given a copy of S.D.
3.1.1, Tagging, determine the l-appropriate course of action in a given situation as it applies to each of tne following: (RS)
- a. Tag issue, placement, recall, and removal
- b. Tagging completeness for a given component
- c. Contaminated tags
- d. Tag stubs e.
Tag voiding
- f. Red and white tag log audits
- g. Human red tags 6.
As required by S.D.
3.1.2, Activities Affecting Station Operation: (R6) a.
Identify the person to be notified if a problem exists or is suspected with the operability of safoty-related equipment.
- b. State the action to be taken prior to-initiating actions affecting unit operation or control room indications.
- 7. Given a copy S.D.
3.1,2, Activities-Affecting Station Operation, determine who should operate a-given valve. (R7)
Describe the approval required to use_the additional:DW makeup pump.
- b. Apply the directive requirements concerning DW consumption and cross-connecting to a given situation.
- 9. Given a
copy of S.D.
3.1.4, Control Rocm Access and Authority: (R9)
- a. Determine the personal who may grant permission to enter the Control Room, l
Rev. 06 /10-15-91/GCW.
i
I OP-OC-ADM SD Februory 19, 1985 MDT/
Page 9-of 24 LRO TRAINING OBJECTIVES
- 10. Given a cepy of S.D.
3.1.6, Station Labeling: (R10)
- a. Determine individual responsibility in implementing the Station Laboling Directive.
- 11. Given a copy of S.D.
3.2.1, Work Request: (R11)
- a. Describe the proceus for initiating a maintenance work request.
- b. Describe the method to void a work request.
- 12. Given a Copy of S.D.
3.2.4, Drum Control Program: (R12)
- a. Determine individual responsibility in obtaining, using and-).abeling drums.
- 13. Given a copy of S.D.
3.3.1, Personnel Dose Control: (R13)
- a. State whether or not given work must be performed under an CRWP or RWP,
- 14. In accordance with S.D. 3.3.1, Personnel Dose Control: (R14)
- r.. State when personnel dosimetry must be worn.
- b. State the five(5) whole body dose and internal exposure administrative limits.
-15. Given a copy of S.D.
3.3.2, Radioactive Material-Controla (RIS)
- a. Determine whether a given area is within the restricted.
area, raciation control area, or controlled area,
- b. Determine whether an item with a given description should-be green or yellow-tagged.-
- c. Determine the appropriate personnel and equipment contamination monitoring, as weil as the correct monitoring equipment to use, for egress -from a given area.
Rev. 06 /10-15-91/GCW
t OP-OC-ADM-SD February 19, 1985 MDT/
Page 10 of 24 LRO TRAINING OBJEC'1'IVES
- 16. Giver. a copy of S.D. 3.3.4, RadiatioA Access Controls (R16)
- a. Determine li' the requirements for high radiation area (HRA) access control are met for a given situation.
- b. Select the proper response to an llRA access control degradation.
- 17. Given a copy of S.D.
3.3.5, ALARA Program: (R17) a.
Explain how stated ALARA practices apply to given situations.
- 18. Given a copy of S.D.
3.3.8, Process and Area Radiation Monitora: (R13)
- a. Determine whether or not Operations is responsible for a given RIA.
b, Apply the Operations ' responsibilities from the directive to given situations.
- c. Determine whether or not Operations compensatory actions are required for an inoperable RIA, and state those compensatory actions required.
- 19. Describe in your own words each of the following security
- areas, as defined in S.D.-
3.4.1,
-General Security Requirements: (R19)
- a. Owner Controlled Area b.
Protected Area
- c. Vital Area
- 20. Decribe the propar use of personal; protective, equipment at ONS,.per S.D.
4.1.1, Personal Protective Equipment. (R20)
- 21. Given a copy.of S.D.
4.1.2, ilse of Scaffolds and Portable:
Ladders:-(R21)
Determine whether or not a ladder is-being properly used, inspected, or. stored for a given situation.
l Rev. 06 /10-15-91/GCW-
OP-OC-ADM-SD February 19, 1985 MDT/
~Page 11 of 24 LRO TRAINING OBJECTIVES
- 22. Given ' a copy of S.D.
4.1.3, Personnel Safety Area Access:
(R22)
- a. State what each individual type of barrier tape and warning sign indicates, b.
Describe the operators' responses to given situations directly or indirectly related tot
- 1) Quench tank cavity entry with normal RCS temperature and pressure.
- 2) Containment entries when RCS temperature is above 300*F.
- 3) Containment entries when the reactor is critical.
- c. Determine whether the proper procedure for entry into a confined space is being followed in a given situation.
2 3. Given a copy of S.D.
4.1.5,-Personal Injury Trcatment: (R23)
- a. Determine the proper actions for a minor injury.
- b. Describe the appropriate control operator-response to injuries requiring MERT activation.
~
- 24. Discuss the two-(2) responsibilities offthe control operator:
during a fire or fire drill, according to S.D.
4.2.2, Fire l
Brigade Organization and Training. (R24) 1 Rev. 06-/10-15-9A/GCW
-l
._L
_~
L OP-OC-ADM-SD February 19, 1985 MDT/
Page 12 of 24 LHO TRAINING OBJECTIVES
- 25. Describe the action to be taken if an impai. ment of a given fire protection systora component is discovered, according to S.D.
4.2.3, Reporting of Fire Protection Impairment. (R25)
- 26. Given a copy of E.D.-4.3.3, Waste Oil Management Program:
(R26)
- n. Determine which group is responsible for a given batch of waste oil.
b.
Describe.the operations' responsibilities for a given batch of turC u building sump or SSF waste oil.
- c. Describe the actions to be taken if an oil spill occurs.
3 p
Rev. 06 /10-15-91/GCW
OP-OC-ADM-SD February 19, 1985 MDT/
Page 13 of 24 LSO TMINING OBJECTIVES Tbc stuoent will be able to do the following:
TIME:
6 llours
)
A. Terminal ('bjectives
- 1. Apply the appropriate Station Directive (s) to given situations, either using a copy of the directive or from memory as required.
B. Enabling ObjectiveH
- 1. Given a copy of Station Directive (S.D.) 2.2.1, Station Procedureus (R1)
- a. State when a
procedure change would be deemed necessary,
- b. Determine the validity of a procedure control copy check.
]
- c. Determine if a procedure must be in the user's possession prior to its performance.
- 2. State when actions not covered by or deviating from approved procedures may be perf ormed, according to S.D. 2.2.1, Station Proceduren. (R2)
- 3. Given a copy of S.D.
2.2.2, Independent verification (R3)
- a. Determine whether a given example is a proper method to identify a component's status,
- b. Determine whether or not independent verification is required for a given component or system.
- c. Apply the precautions listed in the directive to given situations.
4.
Select a correct method for independent veriiication, given soveral choices, in accordence with S.D.
2.2.2, Independent Verification. (R4) 5.
For a given. situation, evaluate whether or not independent verification may be appropriately waived in accordance with S.D.
2.2.2, Independent Verification. (RS)
Rev. 06'/10-15-91/GCW I
T 4
4 Op-OC-ADN-SD February 19, 1985 MDT/
Page 14 of 24 1.50 TRAINING OBJECTIVES
- 6..#;tven a copy of S.D. 2.3.5, Control of Temporary Modifications (TSM): (R6)
Determino whether or not a given item is, by definition, a TSM.
- b. Select the appropriate unit to authorize installation and maintain log entries concerning a
TSM for a
given component.
7.
In reference to S.D. 3.1.1, Tagging: (R7)
- a. Identify those who are responsible for issue and recall of operations' tags,
- b. State the general purpose of red, white, and yellow tags,
- c. State the general purpose of block tagouts.
- 8. Given a copy of S.D. 3.1.1, Tagging, determine the appropriate course of action in-a given situation as it applies to each ct the-followings (RD)
- a. Tag issue, placement, recall, and removal
- b. Tagging completeness for a given component
- c. Contaminated Tags
- d. Tag Stubs
- o. Tag Voiding
- f. Red and white tag log audits
- 9. Human red tags Rev..06 /10-15-91/GCW i
~
i OP-OC-ADM-SD rebruary 19, 1985 MDT/
Page 15 of 24 LSO TRAINING OBJECTIVES
- 9. Given a copy of S.D.
3.1.2, Activities Affecting Station t
Operations (R9)
- a. List two (2) sources available to aid in making operability determination.
i
- b. List two (2) actions required of the shift supervisor whenever a unit exceeds a Tech Spec. LCo.
- c. Determine whether an item is clearly inoperable or must be evaluated to determine its status, d.
Determine when an action statement-begins for a given situation.
o.
Select the appropriate time-frame for beginning maintenance or testing activities on a unit entering an LCO requiring equipment restoration.
- f. Determine who should operate a given valve.
- 10. Given a copy of S.D.
3.1.3, Demineralized Water (DW): (RIO)
- a. Describe the approval required to use the additional DW makeup pump,
- b. Apply the directive requirements concerning DW consumption and cross-connecting to-a given situation.
- 11. Concerning S.D.
3.1.4, Control Room-Access. and Authorityr (R11)
- a. Select from given choices those individuals requiring permission to enter the control; room.
l
- b. List the three (3) positions authorized to grant control-room Access.-
Rev. 06-/10-15-91/GCW-a
7 l
OP-OC-ADM-SD February 19, 1985 MDT/
Page 16 of 24 LSO TRAIN!!1G OBJECTIVES
- 12. Given a copy of S.D.
3.1.6, Station Labeling: (R12)
- a. Determine individual ror,ponsibility in impicmenting the Station Labeling Directive.
- 13. Given a copy of S.D.
3.2.1, Work Requests (R13)
- a. Describe the process for initiating a maintenance work request.
- b. Determine and assign priority for a given work situation.
- c. Complete the additional information on the work request
- form, as required for priority 1,
21,and SF classilications, for a given work-situation.
- d. Describe the process used to determine the Q.A. condition for a given pj970 of equipment.
e.
Determine whether a retest or functional verification for a given component is required.
f.
Identify the person responsible to decide whether or not quality control (Q.C.) is required.
- g. Describe how to determine whether or not clearance to begin work must be obtained.
- h. Determine when clearance to begin work may be given.
- 1. Determine whether or not reclearance to begin work must be obtained.
J. Determine whether or not the equipment is environmentally qualified (RQ).,
- k. Describe the method to void a work request.
- 14. Given a Copy of S.D. 3.2.4, Drum Control Programt (R14) a, Determine individual responsibility in obtaining,-using and labeling drums, i
p Rev. 06 /10-15-91/GCW.
u
. ____ __ _ a
~
OP-OC-ADM-SD February 19, 1985 MDT/
l Page 17 of 24 LSO TRA7NING OBJECTIVES
- 15. Given a copy of S.D.
3.3.1, Personnel Dose Controit (R15)
- a. State whether or not given work must be performed under an SRWP or RWP.
i
- b. Describe the process and required approvals necessary for a given done extension.
- 16. In accordance with S.D. 3.3.1, Personnel Dose controit (R16)
- a. State when personnel dosimetry must be worn.
- b. State the five (5) whole body dose and internal exposure administrative limits.
- 17. Given a copy of S.D.
3.3.2, Radioactive Material Controit (R17)
- a. Determine whether a given area is within the restricted area, radiation control, or controlled area.
- b. Determine whether an item with a.given description should be green or yellow-tagged.
I
- c. Determine the appropriate personnel and equipment contamination monitoring, as well as the correct monitoring equipment to use, for ogress from a given area.
- 18. Given a copy of S.D. 3.3.4, Radiation Access Controls t (R10) t l
- a. Determine if the requirements for high radiation area (HRA) c.ccesa control are mot'for a given-situation.
l b.
Select the proper response-to an HRA. access control l
degradation, l
- c. Describe the controls proscribed for;use of permanent HRA keys and tempornry HRA padlock. keys as they apply to given situations.
- 19. Given a copy of S.D. 3.3.5, ALARA Programt (R19)-
- a. Explain how stated ALARA practices apply.to given situations, - both from - an :individuni and a supervisory perspective.
l-Rev. 06 /10-15-91/GCW-
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Page 18 of 24 LSO TRAINING OBJECTIVES
- 20. Given a copy of S.D.
3.3.7, Respiratory Protection Programs (R20)
- a. Determine individual responsibility in the proper uso of respirators.
- 21. Given a copy of S.D.
3.3.0, Process and Area Radiation-Monitors: (R21)
- a. Determine whether or not Operations is responsible for a given RIA.
- b. Apply the operations' responsibilitius from the directive to situations.
- c. Determine whether or not operations compensatory actions are required for an inoperable RIA, and state those compensatory actions required.
- 22. Describe in your own words each of the following security
- areas, as defined in S.D.
3.4.1, General Security Requirements: (R22) a.
Owner Controlled Area b.
Protected Area c.
Vital Area d.
Normally Unoccupied Vital Area
- 23. Describe the shift supervisor's responsibility for containment-access
- control, according to S.D.
3.4.3, containment Access Control, during all phases of plant operation. (R23)
- 24. Decribe the proper use of personal protective equipment at ONG, por S.D.
4.1.1, Personal Protective Equipment. (R24)
'5.
Given a copy of S.D.
4.1.2, Use of Scaffolds and Portable Ladders: (R25) a.-Determine whether or not ladder is being properly used, inspected, or stored #or a given situation.
~Rev. 06 /10-15-91/GCW
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Page 19 of 24 i
i i
f LSO TRAINING _ODJECTIVES l
- 26. Given a copy of S.D.
4.1.3, Personnoi Safety Area Access :
1 (H26) i
- c. state what each individual type of barrier tapo and a
warning sign indicates.
- b. For a given situation, determine whether or nc+. to j
isolate the SSF-CO system.
1 i
i C. Describe the operators' responses to given situations directly or indirectly related to
{
i i
- 1) Quench tank cavity entry with normal RCS temperature i
and pressure.
[
- 2) Containment entries when RCS tcmperature is above 4
300*F.
i
- 3) Containment entries when the reactor-is critical.
- d. Determine whether or not the proper procedure for confined space entry and the final inspection. af ter a confined space entry-have been performed in a given situation, r
- o. Specify the appropriate response for work in a heat stress environment in a given situation.
- 27. Given a copy of S.D. 4.1.5, Personal Injury Treatments (R27) f
- a. Determine the proper actions for a minor injury.
- b. Describe the supervisors' responsibilities in a given medical emergency.
r
- 28. Discuss three-(3) of the responsibilities of a supervisor ___
acting-as fire brigade captain or lieutenant in response to-
{
a fire,'according to S.D.
4.2.2, Fire-Brigade Organization and Training. (R28)-
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Page 20 of 24 1.S0 TRAll11tJG OBJECTIVES
- 29. Given a copy of S.D 4.2.3, Reporting of Firo Protection Impairments (R29)
- a. Classify the impairment lovel for a given inoperabJe picco of fire protection equipment.
b.
Describe the actions to be taken as a result of a given fire protection system impairmont.
- 30. Given a copy of S.D.
4.3.3, Used 011 Management Programt-(R30)
- a. Determine which group is responsibio for a given batch of wasto oil,
- b. Describe the Operations' responsibilities for a given batch of turbine building sump or SSF waste 011.
- c. Describe the actions to be taken if an oil spill occurs.
- 31. Given a copy of S.D.
4.5.3,' Qualified Reviewers (R31)
- a. Specify whether or not a given change or determination must be reviewid by a qualified reviewer.
- b. State the qualification to perform a cross-disciplinary review.
- 32. Given a copy of S.D, 4.5.4, O.A.
Condition Determinations (R32)
- n. State the three (3) categories of work requests where
. operations would make a Q.A. condition classification,
- b. Determine the proper method (s) for determining a given item's.Q.A. condition.
Rev. 06 /10-15-91/GCW l
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l LPRO - TRAINING ODJECTIVES l
The student will be able to:
Time Variabl_o Hours A. Terminal Objective
~
Decome familiar with and be able to uso and follow the requirements and'information contained in tho operations Manual.
B. Enabling Objectivos j
i 1.
De able to recito, from memory, any required proceduro or administrativo items as detailed in OMP 2-1, Enclosuro 4.5:
(R1) i
.2. The student is not roquired to ho able to list-cach item
~
in Enclosure 4.5 from memory.
i
- b. The "tudent is expected to be able to recall from memory l
thode actions or statomonts 11stod in Enclosure 4.5 as they relato to the specific task or evolution being performod.
- 2. When given a copy of the Operations Manual,-or-portions
- thoroof, be able to demonstrato an understanding of the guidance or rules within specific OMPs by locating the answer to or interpreting required responses for a given situation.
(R2) l l
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Page 7 of 14 LPSD - TRAINING OBJECTIVES The student will be able to:
Times variable hours A. Terminal Objective Romain or becomo f amiliar with and bo able to uso and follow the requirements and information contained in the Operations Manual.
B. Enabling Objectivos
- 1. Bo able to recito, from memory, any required procedure or administrativo items as detailed jn OMP 2-1, Enclosuro 4.5 (hl)
- a. The student is not requiredIto be ablo to list each item in Enclosuro 4.5 irom memory,
- b. The student is expected to be able to recall from memory thoce actions or statomonts listed in Enclosure 4.5 as they relato to the specific task or-ovolution being performed.
- 2. When given a copy of the Operations Manual, or portions thereof, be able to demonstrato an understanding of the guidance or rules within specific OMPs by locating the answer to or interpreting required responses for a given situation.
(R2) i.
l Rev. 07 09/09/91/GCW; LL
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OP-OC-ADM-SRG
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May 6, 1988 LMH/
Page 4 of 14 LRO - TRAINING OBJECTIVES The student will be able to:
Time: Variabit A.
Terminal Objectives Relato procedures and technical documents to the Reactor Operator's (RO) ability to safely and efficiently perform required duties and tasks in-the-plant.
D.
Enabling Objectives:
1.
When given plant / system / component conditions or problems refer to the appropr. tate proceduro(s) and be able to:
(R1) a.
diagnose the cause of the problem b.
Identity the location of t problem c.
indicate apprerriate recuperative actions or actions required to achieve a specified effect d.
identify preceding events and/or actions e,
classify or indicate if the conditions meet specified criteria f.
exp)ain the correct method for porforming an applicable procedure step =
g.
locate and identify the answers to specific questions on limits, cautions, notes, etc... within the procedures h.
deter.'.ine applicable limits or limiting conditions for operation and describe the: required compensatory; measures as detailed in.the Technical Specifications 2.
When given a proposed / hypothetical course.of-action or-recommendation determine the acceptability of the action or recommendation. (R2) 3.
When given a plant condition and/or procedure step (s) explain the purpose, basis or reason for associated specific limits, cautions, notes or procedure steps etc... relating to reactor operator duties. (R3)
Rov. 03/02-22-91/JMB-
-4 OP-OC-ADM-SRG May 6, 1983 LMH/
Page 5 of 14 I
4.
When given the applicable data be able to make correct i
paramotor computations. (R4) 5.
When given a set of plant conditions and/or reactor operator actions be able to predict plant / system / component response, or the effect on the.
same or other systems or components. (RS) 6.
Demonstrate an understanding of the guidance or rules in procedures by locating the answer to specific RO related questions. (R6)
^
7.
De able to recite, from memory, required procedural or administrative items detailed in Operations Manual Procedure 2-1 (OMP 2-1, ENCL. 4.1). ( R'/ )
8.
For AP's, OMP's, SD's Tech Specs and the EOP, l ocomo familiar with the content of each so as to be able to answer, from memory, questions relating to' general systems alignments, available operator controls and instrumentation, bases for specific actions, and in the case of the EOP, the order of priority assigned for mitigating simultaneous casualties. (RO)
Rev. 03/02-22-91/JMB
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Page 6 of 14 LSO - TRAINING OBJECTIVES The student will be able to:
Time: Variable A.
Tarminal Objective:
Relate orocedures and technical documents to the Senior Reactor Operator's (SRO) ability to safely and officiently perform required duties and tasks in the plant.
B.
Enabling Objectives:
1.
When gives.. ant /systam/ component conditions or prcbloms refer to the appropriste procedure (s) and bn able to:
(R1) a.
diagnose the cause of the probles' b.
Identify the location of the problem c.
Indicate appropriate recuperative actions or actions required to achieve a specified effect i
d.
Identify preceding events and/or actions o.
classify or indicate if the conditions meet specified criteria f.
explain the correct method for performing an applicable procedure step l
9 locate and identify the answers to specific questions on limits, cautions, notes, etc... within the procedures h.
determine applicable limits or limiting conditions for operation and describe the required compensatory measures as detailed in the Technical Specifications 2.
When given a proposed / hypothetical course of action'or recommendation determine the acceptability of the action or recommendation. (R2) 3.
When given a plant condition and/or procedure step (s) explain the purpose, basis or reason for_ associated specific limits, cautions, notes or procedure steps etc...
relating to senior reactor operator duties. (R3)
Rev. 03/02-22-91/JMB
t OP-OC-ADM-SRG May 6, 1988 LMH/
Page 7 of 14 4.
When given the applicatle data be abic to make correct parametec computations. (R4)
S.
When given a set of plant conditions and/or senior reactor operator actions be able to prodict plant /nystem/ component response, or the effect on the same or other systems or components. (RS) 5.
Demonstrate an understanding of the guidance or rules in procedures by locating the answer to specific SRO related questions. (R6) 7.
Be able to recite, from memory, nequired procedural or adrdnistrative items detailed in Operations Manual Pracedure 2-1 (OMP 2-1, ENCL. 4.1). (R7) 8.
For AP's, OMP's, SD's Tech Space and the EOP, become familiar with the ccntent of each so as to be able to nnswer, from memory, questions relating to general systems alignments, available operator controls and instrumentation, bases for specific actions, and in the case of the EOP, the order of' priority assigned for mitigating simultaneous casualties. (RB) t I
l l
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Reviewed By
'l I E1g Approved By [ L I CC -
Date il Dace % er.
2001 Revision a 20 OCONEE NUCLEAR STATION OPEP.ATIONS MAhAGEMENT PROCEDUKE 2-1
'DUTIESfAND. RESPONSIBILITIES SF ON SHIFT orERATION$' PERSONNEL 1.0 Purt ose The purpose of this OMP is tos 1)
Define the role and responsibilities of_the Shift Supervisor 2)
Define the responsibilities of the Licensed-Reactor Operators ~on the Control Board.
3)
Define the responsibilities of the SR0 in the Control Room.
4)
Define the responsibilities'of the Unit Supervisor.
53 Detcribe the " normal" lines of cor.inunication and Shift organizat ion to be used during plant operation.
6)
Define tha responsibilities of the non Licensed operators.
i 7)
Define the boundaries which limit the movements of the required Control Room personnel to ensure that the controls are adequar.ely monitored.
l Definei hora procedural items which! Reactor CperatorsTand' Senior-'
8) t Reactor operato3s, shall.have: committed tof memoryr 9)
Define'a control. Board Walkdown
-- p 20 19ferenceg,
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Technical Specification 6.1.1.3 Technical Specification 6.1.1.7-
[2.
}2 N Emergency Oparating Procedure ETQS' Manual Abnormal Procedures Operations Manual operating Procedures Station Directlves MAJOR REVISION-
OMP 2-1 hge 1 of 2 I
i ENCLOSURE 4.1 SHIFT ORGANIZATION AND LINES OF COMMUNICATION Shift orr.ani z a tlatl 1.
The Shif t Supervisor is responsible for the safe operation of the entire station for the duration of his/her shif t and is accountable for the quality of that operation.
The Operators assigned to a particular shift 1
will report to the Shif t Supervisor administrative 1y and organizationally.
The Unit Supervisors will report to the Shift Supervisor and are responsible for the safe operation of their assigned units. The Control Room SRO will report to the Shift Supervisor administrative 1y and a
organizatior, ally, but will report to the Unit Supervisor functionally with regard to the operatien of his/her assigned unit.
2.
The Reactor Operators assigned to a Control Room will report to the Control Room SRO functionally.
Most directions given to the OATC or the BOP Operator (s) will come through the Control Room SRO.
The Unit Superviser may, yjfh the concurrence p,.f the Control Room SRO, give directions to the 0ATC and/or the BOP Operator (s) for specific tasks or evolutions.
{
Emergency Control Room communications will be in accordance with OMP 1-18, l
COMMUNICATION AND EOP IMPLEMENTATION STANDARD.
I t
3.
Itenlicensed Operators (NL0s) will receive jobs f rom and report job status to the same individual whether it is the Unit Supervisor, the Control Room SRO, or one of the Reactor Operators assigned to a Unit.
Overt ime CoverJULe 1
1.
Operators reporting for NLO overtime duties should be treated like the reo9esting shif t's NLO with regard a radiation dose and ALARA practices.
2.
Reactor Operators in on ovartime should not be utilized as the OATC on ar.
outage unit or a unit andergoing major transients.
3.
Overtime will be requested on su "as needed" basis by the Shif t Supervisor or his designee.
1 p nes of Communicatdp.n on shift co municatiqqt j
Owing to the complexity of the shif t organization, strong, well-defitted-lines of communication are estabi.lshed and maintained to succeed ir. the safe operation of-Oconee Nuclear Station.
Every rumber of the shif t team is reqwred to keep the other members of the team taformed of the : status of their watchstation or assigned tasb and, of any abnormal condition discovered during the course of their shif t. -
1.
The "nNav communications (unit directions, work flow, etc.) will be from the. Unit Supervisor to the Control Room SRO. to the Reactor Operators.
~
The Unit Supervisor, the Control Room Supervisor.' or the Shif t Supervisor may assign NLC tasks as usedqd but_ the R0s will generally assign tne -
l.
routine NLO tasks.
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CMP 2-1 Page 2 ef 2 F.NCLOSURE 4.1 shift ORGAN 17ATION AND LINES OF COMMUNICATION on shift qpmmunicatio_gi (cont'd) 2.
All Control hoom personnel. SRO. 0ATC. and 20P, will be informed of any major change to unit status prior to making the change, if intentional, or as soon as possible af ter discovering the change, if unintentional. Minor changes (starting and stopping of minor pieces of equipment, pumping sumps, etc.) may be communicated after the fact.
3.
The Unit Supervisor will be informed of al;.ntentional major changes to unit status prior to the change being made. rie/She will be informed of any unintentional changes to unit status as soon as possible after their h
discovery.
4 The Shift Supervisor will be informed of any m6jor changer to unit status as soon as practical and bef ore turnover to the oncoming sh5 ft.
All Ros working on a unit will keep each other informed as _tu the status S.
o f t.he ' ' unit at all times.
Ofi shift p unications 1.
Operations Staff personnel will give directions / orders to the Unit Superviscr.
The Staff will take particular caro when discussing unit status in the Control Room that their remarks are r.ot misinterpreted as directionr/ orders to the CR SRO or the R0s.
2.
The responsibility for the safety of the unit and the station rests with the-shif t SR0s. This responsibf11ty will be consideret prior to accepting any directions or orders from members of th6 00s _ Staf f or f rom other groups.
3.
All Work Requests, pts. Station Hodifications, etc. will be previewed by the Unit Opertricns Staff prior to clearance approval being given by the Unit Supervisor. All SRos always have the attthority to give clearance for emergency or immediate attention work. Operations Staff personnel may give c12arance to begin work if unit operating status is not affected.
4 All Work Requests. pts, ' Station Modifications, etc. will be processed through the Unit Super isor before presenting them to Control Room personnel for action.
The Control Room SRO will ILql,' accept any work packages without having the packages first approved by the Unit Supervisor.
5.
In the absence of the Unit Supervisor, the Shift Supervisor may, at his discretion,' approve work packages (WRs, NSMs. pts, etc.) for handling by Control Room personnel.
9
OMP 2-1 page 1 or 2 ENCL.0StlRE 4.2 RESPONSIBILITIES OF THE SHIFT St:PERVISOR 1.
The Shift Supervisor is responsible for the safe operation of Oconu Nucicar Station for the course of his/her assigned shift.
He is the primary contact for all of f normal events and emergencies.
1;e rmas t n.aintain a " big pictuie" awareness of a!1 f acets of station operation.
2.
The Shif t Supervisor, during any event requiring entry into our Emergency plan, will perform the function of the Emergency Coordinator until relieved by the Station Manager or his designee.
3.
The Shif t Supervisor is responsible for ensuring that the membecs of his team comply with our occupational safety and ALARA rules and regulations.
The Shif t Supervisor is responsf ble for ensuring that his shif t operates 4
the plant in a manner consistent with the high standards of quality expected of the ONS operations Group.
This requires an active participation in plant operation on the part of the Shift Supervisor.
5.
The shif t Supervisor is responsible for the development of the members of his shift team.
He must instill the need for conservative operation and decision making in his team members. He has-to be involved in the process of training his team members.
Ce must participate in the development of his Assistant Shift Supervisors in -e " hands on" manner and provide an environment suitable for the development of the non-exempt members of his team.
6.
The Shift Supervisor should strive to establish operational consistency among the members of his shif t.
Those individuals fulff111ng the role of relief Shif t Supervisor have the opportunity to monitor operations across -
individual shif t boundaries and should attempt to attain c.onsistency from shift to shift by reporting inconsistencies, both good-and bad, to the Shif t Operations Manager or the Superintendent of Operations.
7.
The Shift Supetvisor is the " coach" of his assigned team.
He is responsible for coaching and counseling the members of his team to ensure that Operationa' expectations are communicated and understood. He is also responsible for saaping the morale of hia assigned team.
8.
The Shif t Supervisor is respot.tible for providing " Management overview" of the way that we conduct Operat. ions' business on a day to day basis.
He must ensure that our. communications techniques and team skills are practiced in the plant as well as -in the simulator.
In addition, the f
Shift Supervisor is required to periodically observo the interactions-between the Shif ts and the Ops Staff personnel to ensure that information ar.d direction follows the prescribed " chain of command".
9.
The "hift Supervisor must insure that approved-procedures and administrative policies are used to assist in :.he control of evolutions af fecting the pl ant. This includes all. groups w rking at the station, not just the Oper4.tlont group, 2
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OMP 2-1 Page 2 of 2 t
ENCLOSURE 4.2 RESPONSIBILITIES OF 1HE SHIFT SUPERVISOR 10.
The Shift Supervisor is responsible for the following items: (espec:. dly during outages or high work load times) a) Attending at least one of the outage meetings daily in order to
=
keep his team better inforrnd of plans and changes to the schedule.
b) Vork with the Ops Staf f to provide ar.d req. nest overtime coverago as the wotg load requires.
c)
Stress quality of operation above productivity, including the use of mini-huddles and/or pre-job briefings to discuss the progress and plans for current evotutions.
These discussions should include expected results (before the evolution). and achieved results and the reasons for not achieving expated restilts (af t er. the evolution),
d)
Ensure that the members of his team take ample breaks in order to maintain peak performance. This is not limited to protecting the-. operators from physical exhaustion, but includes-using.
breaks to re'ieve stress and refresh the minc t of the operators as well, 11.
The Shif t Supervisor is required to aesist in the training of his shif t team members.
This includes conducting NSM/TSM training ensuring thtt routine training packages are completed ir a timely manner, observing -and critiquing the performance of members of his shif t on the simulator and in the plant.
He is also responsible for tee administration of our ETOS program on his shift.
12.
The Shif t St.pervisor is the administrative coordinator for his shif t.
Hfa dutins in this area include the scheduling of physical examinations and training, the p repa rn -- un and presentation of exempt and non-exempt evaluations.
tracking employee
- dore, ensuring that his shift's housekeeping assignments are properly maintained, and documenting and tracking employee time records.
These duties mt/ be delegated to his assistants, but the responsibility fe'. these and other " admin
- functions-rests with the Shift Supervisor.
6
+
4 n
e sG CMP 2-1 Page 1 of 1 ENC 1.05URE 4.3 RESPOSSIBILITIES OF-THE UNIT SUPERVISOR 1.
The Unit Supervisor's position will be filico by an individual holding a current.ly active Senior Reactor Operator license.
2, The Unit Supervisor is responsit'le for the overall operation of the Unit to which he is assigned. This responsibilitj includes operations conducted inside and outside of thr. Control Room.
3.
The Unit Supervisor is responsible for Interacting with individuals from the ops staf f and from ot n' er groups at the station, lle/She will be the p61 mary contact for all k'ork Requests, procedures, and manipulations to be accomplished ott the Unit.
4 The Unit Supervisor will report to the' Shift Supervisor.
The Unit-Supersisor will approve R&Rs prior to their use in the plant.
(Including Control Room RhRs)
The Control Rocm SRO may approve R&Rs pro'vided that he informs the Unit Supervisor and gets his concurrence prior to irrplementing the R&R.
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's OMP 2-1 Page 1 of 2 t
ENCLOSURE 4.4 RESPONSIBILITIES OF THE SRO IN THE CONTROL ROOM 1.
The SRO e.all be required "in - the Control Room" from which the Unit is operated during all medas et glant oper!. tion f rom Cold Shutdown condit!otis te 100% Tower Operations.
"In the Control Room" is defined as inside the CAD key doors that are osed for entering and exiting the Control Room.
2.
The SRO shall ensure hat he/she is propet-ly relieved prior to crossing the boundary listed in +1-above.
Vhrq the Unit is < 20C 'T RCS temperature, the SR0 in the Control Room will be allowed to take 5.nall breaks (less than 30 minutes duration) without being relieved provided that no major evolution or complicated testing in in progress.
3.
The SRO shall report to the Shift Supervisor.
The SRO shal. maintain a " BIG PICTURE" overview of the operation of the 4.
Unit (s) to which he/she is assigned. His/Her funct.lon is to oversee the operation of the unit from the Control Room and to supervise the Reactor Operators in the performance of their duties.-
5.
The SRO's primary concern shall be to ensure the safe _ operation ot' the Unit (s) from the Control Room.
6.
The SRO shall conuuct a formal turnover of Control Room status with the off-going SRO.
7 The SRO shall review Control Room Logs on unit 9) he/she is assigned to.
8.
The SRO shall review unit (s) status by reviewing R&R Logs. Turnover Sheets of Control Operators. Alarm Summaries, and Events Recorder printouts.
9.
The 3R0 shall review with Linit :upervisor(s) their unic status and activities plar.ned during the shift.
10.
The SRO shall make rounds in Control Room to review Control Room status.
11.
The SRO shall review with the Shift Supe. visor the plant status and also inform the Shift Supervisor of his/her planned activittes during the shift.
12.
The SRO shall not take away from any of the established duties or respon-sibilities of the Unit Supervisors.
13.
The SRO shall overses the activities in the' Control Room.
14.
The SR0 may gol provide relief for the Control Room operators.
15.
The SRO sh411 R21 perform any administrative d Aties which may distract from the safe operation of the plant, Such administrative duties shall include.-but not be limited - to, time tickets. shift cleaning program.
ncheduling of other parsonnel.- etc.
GMP 2-1 Page 2 of 2 o
ENCLOSURE 4.4 RESPONSIBILITIES OF THE SRO IN THE CONTROL ROOM 16.
The Control Room SRO will gg,1 prepare R6Rs-or Procedure Changes for use without being properly relieved of his CR SRO duties by another SRO.
He may review and approve R&Rs and may perform reviews of procedure changes and $0.$9 evaluations that have been prepared by others while fulfilling the role of the CR SRO.
17.
The SRO shall become the reader of the Emergency Operating Frocedure (EOP) should its use be required.
The Sko in-the Control Room may designate another SRO as the reader if desired.
18.
The 50.0 is responsible for utilizing eff ective communication techniques per O!'P-10 COMMUNICA!!ON AND E0P IMPLEMENTATION STANDARD.
4 1
I I
_ _ _ _ _ _. _ ~ _. _ _. ___ _ ___._.._ _...._ _._ _ __. _ _.. _._ __ _
UMP b l Page ; og 3 ESCl.05URE 4.5 RESPONSIB!t.ITIES Of THE SEACTCR OPERATORS E,gy,.p_g,qij bi l i t l o s gut M by _ t h e "ntmia t e t at the con t r oj I" WQ!p " B a l a nta
~t p_L13. ant ' ope r a t or 1.
The minimum operating. shif t requit aments for Ret.ctor Operators are defined in OMP 1-2.
The Reactor Operators fulfilling the minimum requirements of Table 6.1-1 of Tn h. Epfe,s.f.. shall ensure that ho/she is properly relieved prior te crossing the boundaries listed in Enclosure 4.4 2.
The Reactor Operators assigned to any Control Room are charged with the responsibility of operating their assigned unit. Thny. are to operate the plant with a questioning attitude. keeping nuclear sofety and " Operations conservatism" in mind.
3.
Reactor Operators have the authority to tage appropriate action (including tripping the reactor) should. In nis/her best judgment. a situat. ion exist requiring prompt-actlon.
4 Prior to making any changes in unit status. Reactor Oper4 tors will refer to all applicable procedures. including controlling procedures, to ensure that all prerequisites for the change are met.
5.
In addition to normal plant monitoring. Reactor Operators are responsible for makirg n Itp.n three complete Control room rounds as defined by.8 of this OMP per shif t.
Thu Operator at the Controls and the Balancs of Plant Operator will relieve each of.her af ter a proper turnover of items in progress in order that these rounds can be completed.
6.
Reactnr Operators shall have the responsibility of notifying the Control Room SRO immediately of any sigaificant abnormal conditions.
7.
Reactor Operators shall have the responsibility for taking the appropriate actions when operating limits of safety related equipment and components.
as described in Technical Specifications or Operating Procedures, are reached or exceeded.
If any of these 11. nits or setpoints are exceeded, he/che shall immediately report this to the Control Room SRO.
r 8.
A Reactor Operator shall acknowledge all alarms.
When an alarm is received, he/she shall take the appropriato actions in response to the alarm. This action may include a comparison / check of-relevant supporting parametsrs to validate the alarm, taking such actions as designated in the Alarm Response Guide, Emergency or Abnormal Procedures. Vhen an alarm is received that is unexpected for the existing plant conditions or without apparent-cause, he/she shall notify the Control Room SRO immediately, 9.
All. Reactor Operators shall ensure that his/her normal or selected instruments monitoring their sssociated parameters are responding as expected for the existing condir.lon.
If an instrument is responding contrary to what would be expected, the redundant-instrument. should be checked to verify the. Indication.
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MP 2-1 Page 2 of 3 ENCLOSURE 4.5 RESPONS!BILITIES OF THE REACT 0h OPERATOPS 10.
Reactor operators, under the assigned authority of the Shif t Supervisor.
Unit Supervisor. or SRO in the Control Room, may direct the activities of other assigned operators (R0s and NL0s).
11.
The Reactor Operator may not delegate his/her responsibilities to non-licensed personnel, but he/she may direct a non-ilcensed person in unit 1
operation for training purposes in accordance with OMP 1-2 RULES OF PRACTICE.
12.
All Reactor Operators are responsible for utilizing el f ac t ivli corrunication techniques per OMP 1-18 COMMUNICATION AND E0P IMPLEMENTATION STANDARD.
13.
Reactor Operators are responsible for t. raining RO class participants on RO ETQS Standards.
They also share in the responsibility to train Non Licensed Opesators on NLO ETQS Standards.
Euronsibilities of_ the "0PEJLt or a t the Cetrols" 1.
The Operator at the Controls (cATC) will be a licensed Operator holding a currently active NRC Reactor Operator or Senior Reactor Operator license.
2.
The OATC thall rnaintain the Reactor Operations Log. All entries into the Reactor Operations Log will be.nade by or under the direction of the OATC during each shift.
3.
Under the direction of the Control Room SRO. the OATC shall have the responsibility for the operation of the assigned unit.
k 4.
The OATC shall provide surveillance of opetations and instrumentation monitored from the Control Room to ensure the safe operation of the Unit.
During shutdown periods, he/she shall ensure that continuous safe shutdo.m
?
conditions exist.
S.
The OATC iball not perform any administrative duties that may distract from the safe operation of the plant.
Such administrative duties shall include, but are not limited to. R&R and Procedure Change preparation, insurance forms, personnel fonns, scheduling of. other personnel, etc.
Responsibilities of the "BaQgce of Plant" Opngqr 1.
The " Balance of Plant" (BOP) Operator will be a licensed Operator holdlug a currently active NRC Reactor Operator or Senior Reactor Operator license.
2.
The BOP Operator is responsible for the monitoring of all ins t rument associated with the particular :ask that holshe is performing at any given time. He/She will verify that plant response to -any control manipulation is as expected prior to continuing with the in progress procedure. If an instrument 's response is not as expected, the redundant tristrument should be checked to verify the indication.
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1, Oe'P ;-1 Page 3 of 3 o
ENCLOSURE 6.S j
RESPONSIBILITIES OF THE REACTOR OPERATORS i
1.
The BOP Operator will keep the OATC and the Cont rol Room ERO informed of l
his/her actions as he/she proceeds with assigned tasks and will inform the DATC and the Control Room SRO of any indication-of trouble or discrepancy j
in the performance of any assigned tasks.
i a.
The BOP Operator shall report information (pertaining to Unit operation) to the Dispatcher as required by the Dispatcher. W/She shall also report I
to the Dispatcher any conditions which indicate that a unit' shutdown or significant load reduction might be nticessary.
I 5.
The BOP Operator will prepare R&Rs for use in the plant as directed by the Control Room 5P.0 or the Unit Supervisor.
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OMP 2-1 Page 1 of 2 j
e ENCLOSURE 4.6 1
RESPONS!BILITIES OF THE NON LICENSED OPERATORS 1
i 1.
Precedutes shall be utilized in the perf ormante of duties required of the NLO.
Use of procedures will. be in accordance with SD 2.2.1 and OMP 1-9.
In order to increase the quality of station procedures, the hLO shall initiate procedure changes that will 1) enhance the prochdures technical content, and 2) make the procedure more efficient.
2.
NL0s are responsible for being safety conscious at all times.
Safety equipment will be used in accordance with 50 4.1.1 PERSONAL SAFETY EQUIPMENT, NLos shall promptly report safety programs to an Operations Su,ervisor.
3.
NL0s are responsible for conducting plant surveillance utilizing round sheets in OP/0/A/1102/20 SHIFT TURNOVER.
Rounds should be made at the i
start of shift and at other Lames as - specified by supervision.
Any abnorma) conditions noted during this surveillance shall be constunicated to the Unit Supervisor, SRO in Control-Room, or the Control Room 0perator so that the impact on plant operations and corrective actions needed can be determined.
In addition to the iter..s on the round sheet, NL0s shall inspect their watch station for material condition discrepancies, safety hazards, and plant cleanliness. Corrective action shall. be initiated for identified items.
4.
NLC are responsible for identifying items.for rep 11r and for initiating work rcquest per SD 3.2.1 WOPK REQUESP.
A HAINTENANCE PUNCHLIST REQUEST can be used to repair items listed under SD 3.2.3 MAINTENANCE ACTIVITIES NOT REQUIRING A WORK REQUEST.
5.
NLos are responsible for knowing and carrying ont the requirements of SD 2.2.2 INDEPENDENT VERIFICATION.
6.
NLos shall Se -fully knowledgeable of and strictly adhere to the requirementr of SL 3.1.1 TAGGING.
7.
As membe r:. of the Station Fite Brigade, NLos are responsible for 1
participating in quarterly drills and annual practical training exercises conducted by the Safety group. They are responsible for carrying out the required actions of SD 4.2.'! FIRE l BRIGADE LRGANIZATION AND TRAINING.
I 8.
NLos share in tha responsibility to maintain plant eqitipment clean.. OMP 2-0 OPERATIONS CLEANING RESPONSIBII.1 TIES ' defines each shif t's cleaning items.
Major cleaMng is-to be performsd on these items.
Small leaks shall be wiped up and contained by the person assigned to that - watch -
station.
SD 2.3.3 REQUEST FOP K-MAC SERVILES may..be utilized for major area cleaning if ' deet..cd necessary by _ the Shif t Supervisor.
9.
It is the tesponsit.llity of the NLO to actively pursue qualification to' the ETQS Program. ETQS qualification is un inttgral part of the promotion -
l criteria of OMP 2-10.. -khon fully qualified t.t the ETQS Program, the NLO t-is responsible for-the traiulng of naw employees to the ETQS Standards.
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UMP 2+1 Page 2 of 2 ENCLOSl:RE 4.6 RESPCNS!BILIf!ES Of THE NON LICENSED OPERATORS 10.
The NLO is responnibic for uttilzing effective communication techniques per CMP 1-18 COMMUNICAT!ON AND E0P IMPLEMENTATION STANDARD.
11.
In the performance of Primary rounds or jobs, the NLO is tesponsible for maintaining radiation dose ALARA per SD 3.3.$ ALARA PROGRAM. NLO& should identify arcas where potential dose savings. exist and initiate ALARA problem reports.
12.
The NLO should effectively utilice study time during Requalification Training in order to maintain a high grade averar,e and to help complete
}
other shift projects.
13.
During the performance of normal duties. NLos should identify potential i
cost savings areas and pursue. irrplementation ' into the Cost Reduction Program.
i 1
14.
The NL0s shall respond to : plant emergencies ;in accordance with the-requirements of ' OMP 1-7 EMERGENCY RESPONSE ORGAN!ZATION.
NLos shal) participate in plant emergency drills as an active participant of the OSC.
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.1 15.
The NLO 6 hall adhere to the requirements of OMP'l-2 RULES OF-PRACTICE.
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o ENCLOSURE 4.7 CONTROL ROOM Bol'SDARIES 1.
Boundaries ectablished for itcactor Operators i
A) k' hen Technical Specifications require one (1) person in the Ccatrol-Room (at the controls), t.his is defined est m+.st be in visible line of Nuclear Instrumentation. See cross hat:heu area on Figures 1 and 2.
B) khen Technical Specifications require two (2) R.0. 's in the Control-Room, one (1) R.0, will be "at the controls" as defined in "A" above and the second R.O. will be inside the CAD key doors that are used i
for entering and exiting the Control Room, i
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o1 OMP 2-1 Page 1 of 1 ENCLOSURE 4.8 C NTkOL ROOM ROUNDS 1.
Each Control Roem Operator will make a complete, detailed board walkdown soon after relieving to verify turnover items and to ensure their understanding of plant and control room equipment.
2.
Around the middle of the shift, a cecond round shoul.1 be conducted to ensure continued proper operation of plant and control room equipment.
3 Toward the end of shift, nich Control Room Operator will again make a complete board walkdo.m paying particular attention to items chaSaed or worked on during their shif t in order to prepare for a de*. ailed turnover.
4 A complete board walkdown vill includei-
- 1) All Controls and corresponding indications to verify valve / equipment status agrees with demand and plant conditions.
All lights should be checked and replaced as required.
s
- 2) All Statalarms in alarm state are understood and are proper for present plant conditions. Those Statalarms out of service should be investigated to f!nd-out why they are out of service, J)
Review of the computer alarm summarias and various display groupa. The display groupt should be used as a cross reference to other indicatione in the control room and to check the status of maior equipment. (RCPs, DIPS, etc. )
4)
All gauges, metert, u d charts should be checked against one another, as applicable, to verify their rea; lings.
9 5)
All "00S" stickers should be shecked for va.dity, reason, and proper attachment,
- 6) Proper operation of control room equipment (typers, RIAs, charts, etc ) should be checked.
5.
Any discrepancies noted during any round will bu brought to the attention of the Control Room Supervisor.
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s' OMP 2-1 ENCLOSURE 4.9 PROCEDURAL., ITEMS VHICH Ali LICLNSED OPERATORS _
t
.5 HALL HAVE.COM.-IITTED T0 MEMORY 0 1.0 Items from the. Emergency Opefating PrecedureI(EP/*/A/1800/01)
.1.1"--Conditions which require entry,into the E0P.
1.2.
Immediate Manual _-Actions-1.3-Significant steps which the Operator shall, be able to_ perform from memory:
1.3.1 If a MS Line rupture gis: indicated then, manually < trip both MFVPs; and c
isolate;the affacted.5G(s):.
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Close A SG f_,,LG EFDW Centrol FDW-315' FDW-316 Main-FDW Bl'ock FDW-31 FDW-40 SU FDW-Block-FDV-33 FDW-42 Main"FDW Control FDW-32 FDV-41 Startup FDWl Cont: 11 FDW-35 FDV-44 Y
1.3.2
' If: either SG c_ level :>E 96% 7. Operating. Range,-~ then^ manually -' trip both FD'ePTs;an0 verify properioperation.of,.EFDW.
1.3.3 It. subcooling, margin-.-c=LO*FTin ' either+1oop eor core. 'then manually trip, a11<.RCPs.within/21 minutes.
1.3.4
Open:
HP-114 ~
HP-? ".
HP-26 HP-27 l
Verifyt running either _ the : A': or f B' f HPI'fmnp' and startithe: 'C' HPI 5
. Pump.,
Verify _ flow;is.sufficientiin both'HPILheaders_withinc10 ninutes.
~
HPI may. be. throttled when Core subcooling margin > 20*F.
Limit HPI? flow.ito 475 gpm/ pump.
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OMP 2-1 Page 2 ef a Encl. 4.9
- 1. 3.1 If;the-Reactor fails =to shutdown or remain-. shutdown =as-required:
7 a)
. Manually.-driven the: Control: Rods into" the' core t
i b)
De-energize,the CRD System s
c)
. Initiate Emergency Boration.of the RCS.
a Opena
' HP-2 4' '
HP-26 HP-25
}
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Verify running"eithar::the.' Af or, ' B' HPI: pump andu start' the
'C'
.HPI pump.:
Verifygproper.flowni.n both.HP1 headers..
i 3
1.3.6 Iftthe abilityato lAed;the SGss.tsost and KC5 pressure 2,r2300: psi r s
t, hen. HPi; forceancooling; twst.: bacinitiatad.
=B21.- forced cooling- - i requires:
Open:
.HP-24 HP-25 HP-26~
HP-27 4
Starts: 7The ' A' gr ??'t HPl.pumpf andnhe 'Ch HPl; pwnp e
Open:
'RC-4.
j RC-66 1.3.7 If.all MFDW;and.; EfDW 1s lo.sti and CDPs m available,3:<depressurize 1
o thc0 SGs-so~Ethat" prinihky" ts" shc6t?dary heat"t' transfer ic'aC be-reestablished usingythe:C3Ps..
J 1.3.8
,1f' Core. rExit4 Thermocouples uitidicate _superheated coaditions. thenPgo
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immediatelysto: the: Inadequate Core Cooling Section-of s ths'EOP 1.3.9 Do not'~ allom the LPIn pumps "io~ run ' for' greater ithan-t 30. minutes -with no florother than miniLum recirc.
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1.3.10 Ife the" ECCS System -ist in operation and 4the 4 BWST> 1evelsroachesT f t.
decreasing.Ftwapa LPI-:suct ion : f rom *the BVSTito the" Emerge 6cy"Sume Ge r=
t.he. EOP.
1.3.11 If HP-24"and 'HP-25 r fai10 to c openo n-ES Chanbel" ivand Yact4at hn; o
V align'HPI in"pifgytiacimode 'aFfollowst v a)-
- Varif y mpenc LP-21, und <LP i 2
b)
Open' LP 9,"LP-16 ? LP-15 and' LP-16 c)
' Star t "A"' or #"B*1I.P!"Pucp '
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OMP 2-1 Page 3 of ',
{.p Encl. 4.9 2.0.; Licensed Operator s are responsibit. for_ knowing lf rom memory the Immediate Manual Actions of-the following: Abnormal.-Proccouress 2.1 5 pent; Fuel. Damage.(APl*/N11700/09)
/
2.1.
Loss;of Instrument. Air-(AP/*fA/1700/22) 2.2 Luss,of Poser-(AP!t/All700/ll)=
4
.1. 3 !a ; eddition _ to the : above... litansed ; operatorst shul. initiate a / manual reactor trip if _ any of the following: cccur
_ Two or more.__CRDI Stators are : > ;180* F.
" Tvo or mora; ControUP.ods:. drop into. the core.
-Either'SGtlove1Lis $il5i",
?
_ BothJiFVPss t rip and tho React.or tisi critical.
Pressurizer 1svel increasesnto > 375+'.-
/
-Uncontrollable flooding _ofythe) Turbine Building.
_ Major damage _can be.seen due:_to(an,oa ghquake or natural disaster.
s Loss of CCV Intake <CanalJor Dam failure.
If; alliIntermediate and Power Ranga Nuclear Jnstrument channels f all i
at-power:and the-Rea'; tor has not tripped.-
3.0 Licensed 0perators.are respcnsibles for..being, able te find. any _ limits, _necessary 5
actions, etc... as described in Technical Specificadions. Joperators::shall also know what - plant components,. systems,; etc..- f alling1under Operations' responsibility.
have Technf. cal Specifications associatediwith'them.
Licensed Operators shall be.able to recall. f ron memory. and initiate La, manual 3.1 e
Reactor trip If,any of: the following Tech; Spec toquited RPS : trip setpoints are exceeded:-
a)
Figh,RCS Pressure 2355 psig.
b)
.High RCS.Temperatur3 f$10*F t
c)
Low RCS Pressure.
r1800 psig d)
Migh;RB Pressure 4.psig; i
e)
High Flux c10515%.
f)
Lors:of Both FDVPTs'
" Loss of both'FDVPTs and the Rx 11s? critical; g)
Turbine. Trip ~.
, y.30% Rx power 7
h)
The :RCP monitors; shall' produce ea6 Reactor trip ufor; the; loss- -of two RCPs and Reactor' power - level < is-greater: than5 22 ;of rated power.
1
^
OMP 2-1 Page z. of 4 Encl. 4.9 N*I*
3.2
-The engineered safety features protective actuation setpoints ?as described in Section 3.5.3 of Technical Specifications sh'al?-be commit.ted to memory.
+
4.0 - 1tems. f tom ops, pts,.etc.,
that llcensed _ Operators shall be able to recall
't i...:
3 memory.
i 2
4.1. If any two of the four NIs become > 2; non-conservative.
have I&C calibrate Nis,. In no case should " Thermal Power Best" exceed Nis by >.4%,
4.2 Any Safety Related Motor Operated Valve that-has been manually. operated must be cycled Alectrical!.y to assure operability.
4.3 - If the LDST level, reaches - 40". docreasing while -the Reactor is ct itical, take-the necessary actions to restore LDST level, s
4.4 Do not 'vperate any_ EFDW pump at > 500 GPM to prevent pump damage.
4.5' MMntain 3 - 6.f t.+ in the UST at all > times when the EEDW= pumps are' required to in operable, o
4.6 -Except-for testing,.theC'i.HPI pump should.not he started unlass: the suction flovpath is aligned ' f rom the~ BWST.
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l ENCLOSURE 5 SIMULATOR FIDLITY REPORT Facility Licensee:
Oconee Nur' ear Station facility Docket Nos.:
50-269, 50-270, 50-287 Operating Tests Administered on:
January 21-23, 1992 This form is to be used only to report observations.
These observations do net constitute. in and of themselves, audit or inspection findings and are not, without furtner verification and review, indicative of non-ccmpliance with 10 CFR 55.45(b).
These observations do not affect NRC certificatt m or approval of the simul #. ion facility other than to provide information which may be used in future evaluations. No licensee action is required solely in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTION AC Lift Oil Pumps At lift. oil-pumps computer point on the OAC computer indicated the pumps were off when they were on and visa versa.
PORV operations The PORV does not operate on the simulator as is described in the lesson-plan, whan normal power is not available.
Fuel-Handling Alarms Spurious fuel Handling alarms were received during an active simulator examination that'were not related to the.
examination.
Reactor Coolant Pump Speed' RCP speed indicat_ ion computer point.on the:
j.
0AC computer indicated the pumps were at-0
- percent speed when they were at 100 percent-and visa versa.
LPI injection /switchover The simulator was unable to model Shut down LPI switchover mode of operations to
.the normal mode of operations.
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MC10_WRL4 NRC RESOLUTION Of_ FACILITLCOMMENTS Comment 1.
Question 26 RO:
Comment accepted. There is a correct answar which is found in the Abnoriaal Operating Procedure (A0P),
i however, in accordance with OMP-2-1, this A0P l
(AP/1/A/1700/07) is not required for memorization.
This question will be deleted from the examination and point value adjusted accordingly. The facility is reminded that procedural-discrepancies 'between_
E0P's and AP's should be resolved as soon as possible.
2.
Question 32 RO:
Comment accepted.
The answer key for "c" 33 SR0:
will be changed to reflect 10 as the correct answer.
l 3.
Question 36 R0:
Comment accepted.
This question will be 37 SRO:
deleted from the exam and point value adjusted accordingly. The facility is-reminded _that accurate technical reviews are r essary to ensure content-validity. The facility is also requc ted to review _.
the corresponding Lesson Plan for technical accuracy.
s 4.
Questior. 39 RO:
Comment accepted.
The answer-key will be.
i 40 SRO:
changed to reflect that "b" and "d" will be accepted -
j.
as correct answers.
5.
Question 45 R0:
Comment accepted. The answer key will be 48 SRO:
changed to reflect that'"d" is the' orly-correct
- answer, 6.
Question 46 SRO:
Comtent accepted. This question will be deleted from the examination _and point 'value adjusted l
accordingly. The facility is reminded that accurate techn5 cal reviews-are necessary to ensure content validi ty.
i 7.
Question'.47 SRO:
Comment accepted. The answer key will be changed to reflect that '"b" and "c" will be -accepted as correct answers.
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Question 48 RO:
Comment acceptoo. -In accordance with 51 SR0:
Operator Licensing Branch policy, questions that have more than two correct answers will be deleted from the exam and point value adjusted accordingly.
9.
Question 53 RO:
Comment accepted. The answer key will be changed to reflect that "b" and "c" will be accepted as correct answers.
- 10. Question 55 RO:
Comment not accepted.
Since response "b" 4
61 SRO:
correctly describes the plant Main Steam Relief valves designed operation, it will be considered the only correct answce.
The answer key will be changed to reflect-"b" as the only correct answer.
- 11. Question 71 R0:
Comment accepted.
The answer key will be 76 SR0:
changed to reflect that "a" and "c" will be accepted as correct answers,
- 12. Question 73 R0:
Comment act accepted.
Providing 70 SRO:
" Pressurizer level increasing" in the stem of the
_ question was not necessary to determine the correct answer.
Choices "a", "c",
and "d" can all be eliminated using basic RCS system knowledge leaving choice "b" as the only possible_ cause _for the pressure increase, i
- 13. Question 86 SRO:
Comment accepted.
a). 86 (b): _ The answer key will be changed to allow "3" as an adaitional correct answer. 'The faci ~lity is reminded that accurate technical reviews are necessary to ensure content-val idity, b). 86 (c) will_ be deleted-and ex Am point value adjusted due to-incorrect wording in Column B, Jchoice 6, which could have led to candidate confusion.
It should be noted that none of the SRO candidates proposed questions concerning-this distractor during the' examination..The facility is reminded that the pre-exam review:
should also include wnrding and phrasing as well as technical aspects of questions.
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- 14. Question 6a R0:
Comment not accepted. As written the 89 SRO:
question is technically accurate, representing actual piant design.
lne answer will remain the same. The facility is reminded that examinations contain testing material based on current plant configuration.
The NRC as well as studerits must receive current material in order to test the i
applicant's knowledge on the operation and configuration of the plant.
- 15. Questions 9, 26, 27, 31, 39, 42, 43, 44, 45, 46, 47, 48..R0:
8, 30, 32, 40, 43, 44, 45, 46, 47, 48, 49, 50, 51, 5 2, 5 3, 5 4............................. S R0 :
Generic Comment:
Comment acknowledged, it should be noted that NRC examinations are based upon a complex model that is obtained from NOREG/BR-0122, " Examiners Handbook for Developing Operator Licensing Examinations." Topics included in this model are important test items that enable the NRC to determine minimal competence of an operatcr candidate's knowledge to operate a nuclear 3
power plant.
For example:
Questions like R0-45/SRO-48, calculating radiation expasure for an individual, is in K/A category 194001K104 and holds an importance rating of 3.3/3.5. This type of test item enables the NRC to determine the individuals knowledge of the ALARA Program and the operators knowledge of his/her exposure record.
It is anticipated that an operator entering a Radiation area would not necessarily have a copy of S.D. 3.3.1-at the point of entry for prior review.
In addition, in reference to question R0-43, it is anticipated that a Reactor Operator performing independent verification would not review S.D.
2.2.2, " Independent Verification", each and every time he/she were tasked to perfonn this function.
Therefore, test items while not necessarily form fitted to the facilities learning objectives are in the realm of being tested without reference material i
being provided.
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Q a.