IR 05000272/1987021
| ML20237H183 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/17/1987 |
| From: | Collins S, Keller R, Reidlinger T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20237H167 | List: |
| References | |
| RTR-NUREG-1021 50-272-87-21OL, 50-311-87-26OL, NUDOCS 8709030151 | |
| Download: ML20237H183 (89) | |
Text
{{#Wiki_filter:- -_- _ _ _ _ _ _ _ - _ _ - _ _ _ e . . A U.S. NUCLEAR REGULATORY COMMISSION
REGION I
REQUALIFICATION EVALUATION REPORT Evaluation Report Nos.: 50-272/87-21(0L),50-311/87-26(0L) Facility Docket Nos.: 50-272; 50-311 Facility License Nos.: DPR-70; DPR-75 Licensee: Public Service Electric and Gas Company Post Office Box 236 , Hancocks Bridge, New Jersey 08038 Facility: Salem Nuclear Generating Station, Units 1 and 2 . Examination Dates: June 15-19, 1987 Chief Examiner: Wh h Gy fos N4 TEL coni S-6~ 8 l T. D. Reidirfger, ad Reactor Engineer Date Reviewed By: ) I 41 N///7 R. M. Keller, Chief, Projects Section IC, DRP Date Approved By: koil 2%j gg7 S. J. Coll ~ ins, Deputy Director Date Division of Reactor Projects Summary: Seven licensed senior reactor operators (SRO) and five licensed reactor operators (RO) were administered written and operating examinations.
Two SR0s and three R0s passed all portions of the examination.
The requalifi-i cation program was evaluated as unsatisfactory using the criteria of the Operator Licensing Examiner Standards, NUREG 1021, Chapter ES-601, paragraph F.1.
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REPORT DETAILS 1.
Examination Results i R0 SRO TOTAL EVALVATION Pass / Fail Pass / Fail Pass / Fail Written 4/1 5/2 9/3 Marginal Operating 4/1 4/3 8/4 Marginal Overall 3/2 2/5 5/7 Un sati sf actory 2.
Examiners D. Shepard, NRC T. Reidinger, NRC K. Parkinson, Sonalysts , G. Weale, Sonalysts 3.
Exit Meeting On June 19, 1987, at the conclusion of the requalification examinations, the examiners met with members of the plant staff to discuss generic find-ings made during the course of the examinations. The following personnel attended the exit meeting.
NRC Personnel T. Reidinger, NRC D. Shepard, NRC K. Parkinson, Sonalysts G. Weale, Sonalysts Facility Personnel J. M. Zupko, Jr., General Manager, Salem L. K. Miller, Assistant General Manager, Salem L. Catalfomo, Assistant Manager, Operations Training j H. D. Hanson, Manager, Nuclear Training P. Landers, Principal Training Supervisor, Salem Simulator i J. Gueller, Operations Manager, Salem G. A. Roggio, Station Licensing Engineer ) A . _ _ - _ _ __ ---__j
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, l Summary of NRC Comments The examiner presented the following facility strengths.
The plant was extremely clean.
The plant access briefing conducted by the Radiation Department was clear, concise, and professionally presented.
The opera-tors were knowledgeable in the operational aspects of administrative con-trols. An improvement was noted in the communications and control inter-face between the Shift Supervisor and the Emergency Procedure Reader over the course of the evaluation week.
The examiner presented the following examples of the informality of the conduct of operations in the Main Control Room.
The plant was in an action statement which required performance of a grab sample at least once
every 24 hours in accordance with Technical Specification No.
3.3.3.8, Radioactive Liquid Effluent Monitoring Instrumentation. No licensed oper-ator in the Main Control Room was aware of the status of the required grab sample. No turnover on this item had been conducted and no log entries concerning the completion of the grab samples had been made for two days.
Operators maintained an informal posture in the Main Control Room includ-ing leaning against and sitting on the control boards rails.
Control panel's indications were covered by procedures which were being used. The use of the control panel as a book rest was also observed during the simulator examinations.
Some plant personnel did not wear personnel monitoring devices on the front of the torso as required by AP-24, para-graph 6.5.
The examiner presented the following examples of operators' informality and lack of discipline during the simulator scenarios. The annunciator alarm horns were not silenced in a timely manner during major plant casualties which added to the confusion in the control room.
The Shift Supervisors did not require close supervision of tripping of bistables and in one instance the operators failed to observe that an incorrect bistable had been tripped.
Operators did not routinely announce the status of j major equipment failures or plant limitations over the plant page system.
l In one scenario, operators performed a procedural step out of sequence and j potentially placed the plant in an unanalyzed rod drop condition.
l The examiner presented the following examples of calibration and labeling problems at the facility.
The high range count monitor recorder, 2R44A, and several turbine vibration recorders had out of date calibration stickers. On the gas radiation waste panel, WG41, valve interlock lights are not labeled per the gas release procedure On the liquid radiation waste panel, R18, the high alarm light for liquid release is not labeled.
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. The examiner presented the following examples of operators' lack of know-ledge of radiation monitoring equipment. Several operators demonstrated a j lack of ability to operate the Unit 2 Radiation Monitoring System computer
and stated that no training had been provided on the system.
Most of the operators demonstrated knowledge weaknesses in the use and function of some radiation monitoring equipment.
The examiner noted that the simulator did not accurately replicate the Unit 2 control room, and that simulator modifications were on going. The examiner also noted that the reference material provided by the utility for examination preparation was not updated to reflect the -present plant configuration.
4.
Examination Review comments and responses Facility Comment Question 5.01 Key should read 2.
NRC Response: Answer key has been amended.
Facility Comment Question 5.07 Add: Maintain HCFs as an acceptable answer.
NRC Response: " Hot channel factors" has been added to the answer key as an acceptable. alternative for " flatten axial and radial flux profiles."
Facility Comment Question 5.10.a.
Salem Reactor Engineering Manual has only one " core life" rod worth curve.
NRC Response: Noted, the question is asking for rod worth effects over core life.
Lesson Plan for Control Rods for requalification dated 8/27/85 has Figures 8 and 9 labeled BOL showing that examinees have been exposed to concept of different rod worths at various times in core life.
No change has been made to the answer key.
Facility Comment Question 5.13 Question could be asked to include a brief response so that one's own interpretation of " difficult" is not a factor in correctly answering the question.
l NRC Response: Identification of criticality on startup is actually l at a supercritical condition. Answer key has not been l changed.
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. l Facility Comment Question 6.02 The word "all" opens the floodgates.
NRC Response: The utility did not provide additional alternative answers. Answer key has not been changed.
Facility Comment Question 6.03 Operator could draw a reasonable conclusion but the answer may be more general or might include an assump-tion as to why SG Level decreased.
NRC Response: The answer does not require an assumption as to why SG level decreased.
Answer key has not been changed.
Facility Comment Question 6.04 Could trip on 2/4 PR. Answers will probably not get to the OT DELTA T level but will indicate a reactor trip.
The LER that this questions is written from was more complicated than the general conditions of the question.
NRC Response: Answer key has been changed to accept 2/4 high power flux trip as alternate for OT DELTA T trip.
Facility Comment Question 6.06.b Question should describe PT-507.
An operator may assume that it's any steam pressure channel.
Could also trip on steam flow-feed flow mismatch with low level.
NRC Response: Question specifies that PT-507 is steam pressure, in addition, all loop pressure detectors have one, two, three or four as second number. Chapter 27 of Student Notebook (SGULCS) refers to PT-507 as simply steam j pressure and subsequently uses PT-507 exclusively in connection with main feed pump control.
No questions t were asked for clarification by examinees, showing no confusion on their part.
Steam flow-feed flow mis-match with low level is an acceptable alternative to low-low SG 1evel reactor trip.
Answer key has been changed.
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. ! Facility Comment Question 6.08.a,b.
Our operators are not required to " troubleshoot" in-strument failures. They respond to the control action according to available guidance and summon the Shif t Technician.
At Salem, all major disciplines required for prompt, corrective action are represented on shift.
NRC Response: The examinees are not required to troubleshoot, but are given specific, reasonable failures and asked for the rod control system's response. Questions of this type are written at the higher cognitive levels of synthesis and analysis expected of SRO examinees.
See 10 CFR 55.41b7 and NUREG-1020 Chapter, ES 203F, ES 402.A.2 and ES 403E.
Answer key has not been changed.
Facility Comment Question 6.10.a.
Valve closure actually occurs due to a voltage induced pressure instrument spike.
RHR suction valve should be a sufficient answer.
b.
KEY answer is incorrect. A design change was imple- ! mented so that the backup AC feed is from 2B Vital bus and is no longer tagged open.
NRC Responsa: Part a: RHR suction valve name has been accepted for 2RH1 and voltage induced pressure spike has been accepted as an alternative to momentary loss of bus.
' Part b: Answer was written per facility supplied materials, however, answer key has been changed to reflect updated material.
Facility Comment Question 7.01 Answers will probably not indicate immediate release of tags.
Appropriate communications and checks must be made for release of tags. Pump will be restored to operability in accordance with safe work practices and procedures. Answers may include some required notifi-cations and entry into T.S. 3.0.3.
NRC Response: Answer key has been expanded to accept "T.S. 3.0.3" and " write incident report," as acceptable alternate answers,
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, Facility Comment Questions 7.02 Question requires recall level of knowledge of Func-7.04 tional Restorations entered not as a result of Red 7.09 Paths.
This type of question makes almost anything in any procedure " recall level of knowledge."
It also shifts the focus away from " hands-on" use of proced-ures through inferred pressure to "know the steps."
i NRC Response: Question 7.02 is a general procedure question covering-I knowledge related to major actions for a functional recovery which is entered as a result of a yellow path.
Since the operator is not required to take actions for a yellow path the question has been deleted.
i Question 7.04: Answer Key has been altered to accept > the steam generator with low. level.
Question 7.09b: Do not concur, Instructional Objec-tive 1.2 for Lesson Plan 305-145.13-E0P-01, Emergency ) Operating Procedures Review, states, "given a proced- ' ure, explain the reason for each step".
FR HS-1 states the step per the question and no reasons are given in the procedure for this step.
The answer key has not been changed.
l Facility Comment Question 7.03.b.
Key requires procedure number / designator.
We do not , train to this level.
! NRC Response: Component names have been accepted for procedures.
J l Facility Comment i I Question 7.09.a Based on the comments at the Examination Review Meet- ! ing, it appears that the examiner has a problem with j our procedure (s).
!,erators should not be penalized i for this.
j l NRC Response: The terms feed and bleed, and bleed and feed are not i explicitly defined in either the definitior.s in the
Executive Volume or the Writers Guide of the Westing-
house Owners Group Emergenc-.<esponse Guidelines. The ] question has been deleted since these terms are not
definitively defined in either Salem training material nor the Owners Group Guidelines.
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. Question 7.10 Answer key has been changed to "TRUE" based on direc-tions for interpreting Technical Specification pro-vided in Operating Directive 12.
Question 7.14 Question has been deleted based on the low importance rating for knowing when to deenergize the plant per- , sonnel elevator.
' Facility Comment Question 8.02.a.
1 gpm unidentified is not necessarily the only one of that LC0 that applies.
b.
There is also SP(0)4.4.6.2 and OP-II.1.3.5.
i NRC Response: Part a: Since the initial conditions of the question do not identify leakage, it should be assumed uniden-tified.
The answer key has been changed to accept additional leakage LCO.
! Part b: SP(0)4.4.6.2 and OP-II.1.3.5 has been ac-cepted as alternate answers.
Facility Comment Question 8.03.c.
These tests are the responsibility of another respon- , l sible department - In-Service Inspection.
The ques-tion represents 10% of the section.
, l ! NRC Response: The test is not required to be performed by examinees, , However, the definition of the tests as defined by 10
" CFR 50 Appendix J and as used in Technical specifica-tion 3.6.1.2 should be known to properly understand the Technical Specifications.
IOP2 checkoff Sheet I which includes a verification of STS 4.6.1.2(A-D), j Type A, B, and C Leak Tests requires a sign off by the
SSS/SS.
10 CFR 55.43(b)(2) requires operators to be j examined on "Facili ty operating limitations in the l technical specifications and their bases." No change i has been made to the question.
Facility Comment Question 8.04 This Tech. Spec. has been changed since the incident.
A one-hour soak is incorporated.
in addition, the assumption can also be made that the rod is inoper-l able.
l NRC Response: Answer key has been amended to incorporate one-hour i soak.
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. Facility Comment Question 8.06 KEY says Technical Supervisors.
This is a general term encompassing' various radiation protection super-visors. Grading should recognize other titles.
NRC Response: Equivalent terms have been accepted.
Facility Comment Question 1.04 Operators are taught that the power ievel change Xenon peaks occur at 5-6 hrs. A positive to negative cycle should be 11 2 hrs.
NRC Response: Full credit will be awarded for answers that reflect facility comments.
Answer key has been modified.
Facility Comment Question 1.08 There are alternate formulas that could be utilized.
NRC Response: Full credit will be awarded for the correct use of alternate formulas. Answer key has not been modified.
Facility Comment Question 1.09 Solicits bases from Ros.
It is, however, a common knowledge item, although we would normally word it as " list the three..." NRC Response: Job Task Analysis contained in NUREG-1122 assign this knowledge on importance rating of 3.4 for R0's See KA No.
192005K115.
Answer key has not been modified.
Facility Comment Question 1.10.a Could be none if the operator assumes that he/she is looking at the AT meter.
NRC Response: Procedure E0P-Trip-3 " Safety Injection Termination," Step 29.1 has the operator monitoring natural circu-lation by observing the following four specific para-meters.
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, i . . , ! I RCS Wide Range Hot Leg Temperature l S/G Pressure RCS Cold Leg Temperature l The AT meter is r.o t a valid indication of Natural Circulation being established and should not be con-i sidered when answering the question.
The answer key has not been changed.
Facility Comment Question 1.11 Could be True if the operator uses lambda from the supplied formula sheet.
NRC Response: Using lambda from the attached equation sheet will ng result in a stable period of equal magnitude using
l-equal magnitudes of reactivity insertions and the equations supplied on the answer sheets. The answer key has not been changed.
Facility Comment ! Question 1.14 KEY answer should be 2590 i 100. Also, question uses , .99, KEY uses.995.
j NRC Response: Answer key has been revised.
Facility Comment I Question 2.01.a.
Two other correct answers: 1., Loss of Control Air 2.
Loss of 125VDC NRC Response: The question asks for unique signals which will gener-ate a turbine driven auxiliary feed auto start signal.
The other answers provided in the facility comment are not auto-initiation signals. Answer key has been amended to remove loss of offsite power as separate answer.
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, Facility Comment Question 2.01.b.
The Fresh Water and Fire Protection Tank is one tank.
NRC Rosponse: Answer key has been revised to divide credit equally among correct answers.
Facility Comment Question 2.02.b.
We do not rec ire operators to know unobservable con-trol interlock setpoints.
NRC Response: Full credit has been awarded for knowledge of the l interlock.
Facility Comment Question 2.03.b.
There is a backup (accumulator) air supply for the PORVs.
e.
There is no nitrogen supply to the pressurizer spray valve - fails closed.
NRC Response: Answer key has been modified.
Facility Comment Question 2.04.b.
The button actually reads INCREASE.
NRC Response: The question specifically asks for actual valve posi-tion, not button indication. Answer key has not been modified.
Facility Comment Question 2.06 Loading sequence is available to operator on RP-4 Panel in Control Room.
We no not require them to recall the sequence of load application.
NRC Response: The answer key has been modified to accept any four , loads.
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4 Facility Comment Question 2.0.7 Another correct answer is " maintain HSB/Artifical Load."
l NRC Response: The answer key has been modified to accept facility l comment as an alternate answer.
Facility Comment ,
Question 3.05 A0Ps are used "in-hand".
We do not require recall of individual loads on a specific vital instrument bus.
This is available in the procedure.
The procedure would have been furnished if the question was asked on o;r requalification examinations.
In this particular instance, the AOP is written for <P-8 (36%), or no reactor trip.
With power >P-8, a reactor trip would have occurred because the RPS input for RCP Breaker Position (1/4) is fed from this bus.
On a loss of vital instrument power, the RPS believes that an RCP Breaker has opened.
NRC Response: While the subject AOP does not reference the P-8 interlock it is apparent through the additional refer-ence material provided that the answer key is incor-rect.
The answer key has been modified.
Facility Comment Question 3.06.b.
The question is somewhat misleading because it can be misread (especially on a timed examination).
The answer is True but operator action is required to activate the system.
NRC Response: The answer was based on reference material supplied by facility to NRC that had not been revised to reflect current plant configuration.
The answer key has been modified to accept the correct answer, "True."
Facility Comment Question 4.01.a.
There should be allowance for additional reasonable answers.
b.
Same as 4.01.a.
NRC Response: Credit has been awardtd for alternate equivalent answers for both Parts a and b.
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i , NRC Comment Question 4.02 The question was taken directly from the facility sup-plied reference material which was out of date and did not reflect current. plant configuration.
Question 4.02 has been deleted from the exam.
Facility Comment Question 4.04 We test operators in the requalification program in the same manner as they would.be expected to do their l job.
A0Ps are used "in-hand" and, therefore, would be ~ supplied as an examination reference. We then develop ! questions that require analysis or more detailed information concerning procedural steps, precautions, l cautions, etc.
NRC Response: Job Task Analysis contained in NUREG-1122, justify ! ! this question through KA's 000068EK306, EK314 and EK318, assigned importance rating 3.9, 3.2 and 4.2.
respectfully.
The answer key has not been changed.
Facility Comment ' Question 4.05 These questions are developed from steps or other information that is pulled out of a procedure.
The " required level of knowledge is appropriate but we would test it with the procedure available. This type i of knowledge is more appropriately tested on the simu- ! lator, while the procedure is being utilized, or on an I oral examination.
] NRC Response: Job Task Analysis contained in NUREG 1122 justify this question through KA's 000015EA107, A122 and 003000A201, assigned importance ratings of 3.5, 4.0 and 3.5 respectively.
The answer key has not been changed.
Facility Comment Question 4.07 There are some other OHAs.
NRC Response: Answer key has been amended.
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, Facility Comment Question 4.08 These questions are developed from steps or other , information that is pulled out of a procedure.
The required level of knowledge is appropriate but we would test it with the procedure available. This type of knowledge is more appropriately tested on the l simulator, while the procedure is being utilized, or on an oral examination.
NRC Response: Job Task Analyses contained in NUREG-1122 justify this question through KA000008EK303, EA101, EA107 and 010000A204 assigned importance ratings of 4.1, 4.2, 4.0 and 4.1 respectively.
Answer key has not been changed.
5.
Simulator Performance Problems which affected the ability to perform scenarios as written: a.
Simulator overrides did not work on June 16 and 18,1987. The simu- ! lator was unable to perform actions of a nuclear instrumentation failure and was unable to disguise normal sequence of loss of primary coolant accident.
b.
During the second set of scenarios on June 16,1987, S/G 24's level l increased in an uncontrolled manner and then decreased to below the normal operating level without any action on the simulator operator's part or as a result of an inserted malfunction.
, c.
Step counters for control bank D did not respond during rod drop recovery conditions on June 18, 1987.
Equipment identified by facility work requests for incorporation into simulator: a.
Panel 2RP1 IWL71, 72, 73 valves Condensate makeup flow meter CNMT 2R44A/B Trouble Annunciator PAN Alarm panel for various RMS's T41-R45 INTLK-BLOCK, RESET switches 2 Gas Decay Tank recorders RCDT level recorder Hi range CNMT records (2) MN STM LINE RAD recorders (2) HUT level recorders (2) PLT VENT SAMPLE - NOBLE GAS recorder CNMT SVML level recorders (2) RVLIS monitor (on 2RP1)
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Panel 2RP2 l pH, conductivity, phosphate recorders (3) reactor vessel head vent valves c.
Panel 2RP4 i Recirculation semi-auto swapover d.
Panel 2RPS Fire Panel l Condenser Condensate Sodium, Conductivity recorders e.
Back Panel Eccentricity Vibration, Diff, casing Expansion Recorder P-2500 computer console l Facility personnel are aware of these problems and have work orders in place to correct them.
6.
NRC Follow Up During a telephone conversation on July 23, 1987, the licensee was in-formed of the number and types of examination failures. The licensee was requested to take appropriate actions in accordance with its requalifica-
tion program and attempt to identify root causes for the large number of I failures.
The completed operating examinations, the corrected written examinations, and the final written examinations' question and answer keys ! were mailed to the training department on July 23, 1987.
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Conclusion ! Five of twelve licensed operators passed all portions of the NRC admin-istered requalification examination. The requalification training program is evaluated as unsatisfactory based on the guidance provided in the Operator Licensing Examiner Standards, NUREG-1021, Chapter ES-601, para-graph F.1.
The written examination failures appear to be individualized problems based on the disparity between the individuals' grades and the average grades. One contributing factor to the failures on the operating examinations was the problems caused by the communication and control interface between the Shift Supervisor and the procedure reader.
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. The licensee is requested to identify the root cause for the high failure rate and develop corrective actions as provided for in NUREG-1021 Chapter { ES-601, paragraph F.2.C.
The short term and long term corrective actions j should be submitted to the NRC within 60 days.
ATTACHMENTS: 1.
Written Examination and Answer Key (RO) 2.
Written Examination and Answer Key (SRO)
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_ - _ _ _ _ _ _ _ - - _ _ _ _ _ _ .I jh_.*n; ATTACHMENT 2 j
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NUCLEAR REGULATr"1Y COMMISSIO!1 SENIOR REACTOR OPERATOR REQUALIFICATION EXAM 111ATION ' FACILITY: _ S6L}Z _1 &2 .__ REACTOR TYPE: PWR-WEC4 - DATE ADMINISTEl(ED: _E7/0_6119 ._.
EXAMINER: _JtE1]!1HgEBt._1 _ cat;D]DATE: _. _ _ _ _ JNOTBUGT.WNi10_!!6HDIDATE lhed the attached instruction page caref ully.
This examination rep'; aces the current cycle facility administered requalification examloetion.
Ret, raining requirements for failure of this examination are the m.me as for failure o't a requalification examination prepared and administered by your training staff.
Points for each question are indicated in parentheses. afLer the question.
The pancing grade requires at least 70% ! in each category and a final grade of at least 80%. Examination papers
will be pJ ck,ed up f our (4 )' hours af ter the examination starts.
' i , % OF CATEGORY % OF CANDIDATE'S CATEGORY ..J'bh!!8 J HAl, SCOhE___._ _yALUE GbTEggRY _ _ _. _ _ ._ h 0 ! L _ _ M J S __.
___ _.. _ 5. THEORY OF-NUCLEAR POWEk PLANT OPERATION, FLUIDS, AND THERMODYNAMICS _. H 4 O h. _ _1U ...._ _ ___._.
___.__.___ 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION _l!LUk _ _lk..,J1 _ __ 7.
PROCEDURES - NORMAL, AB110RMAL, EMERGENCY AND RADIOLOGICAL CONTROL .. 1!tJ2u__. _U4. J u 8.
ADMINISTRATIVE PROCEDUl(ES, CONDITIONS, AND LIMITATIONS 30s UJ__ .._._ _. % Tota 1s . _. _. _. _ _ _.. Final Grade A13 work done on this e.xaminatico is my own.
I have neither given nor received aid.
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_ _ _ _ _ _ _ _ _ _ _ _ ._ _ - ...
EQUATION SHEET - f = ma v = s/t Cycle efficiency = (. Net work ' ' out)/(Energy in)
w = og s = V,t + 1/2 at t E = ac t g,g,4 KE = 1/2 av ,,gyf,y )fg g, g, c PE = agn v, = v, + at = = e/t A = an2/tifg = 0.593/t1/2
- *EI"W'(W3 W =, aP-ID 1/2
[(g /2 * I# I) I A= -
D , aE = 931 m ,,y Ao-D av g,g
' Q m mCpat 6 = UA A T I"I' o pwr = W ah I"l 10_ g f a TVL = 1.3/u sur(t) HVL = -0.693/u P = P 10 p = p,e*/I , SUR = 26.06/T SCR = 5/(1 - Kdf) CR, = S/(1 - Keffx) SUR = 26p/s* + (s - p)T CR (1 - Kgf3) = CR (I ~ Ieff2)
2 T = (1*/s) + [(8 - eVIo] M = 1/(1 - Kgf) = CR /CR, j T = s/(o - s) M = (1 - K IIII ~ Edf1) dfo T = (s - e)/(Io) $DM = ( -Kdf)/Edf
- = 10 seconds e = (Kgf-1)/Kg f = aKgg/Kdf I = 0.1 seconds-I e = ((t*/(T Kdf)3 * E"df (1 + IT)] -
/ Id I dj =2,2 2 j P = (t4V)/(3 x 1010) Id gd jj
2 1 = eN R/hr = (0.5 CE)/d (meters) R/hr = 6 CE/d2 (f,,g) _ Water Parameten Miscellaneous Conversions I - 1 gal. = 8.345 lem.
1 curie = 3.7 x 1010 ^ dps 1 ga;. = 3.78 liters i kg = 2.21 lbm 1 ftJ = 7.48 gal.
1 ap = 2.54 x 1 stu/nr Density = 62.4 Itg/ft3 1 nw = 3.41 x 1 Stu/hr > l Density = 1 gm/cv lin = 2.54 cm Heat of vaporization = 970 Stu/lem
- F = 9/5'C + 32
! Heat of fusion = 144 Stu/lbm 'C = 5/9 (*F-32) ]Ift.HO=Atm = 14.7 psi = 29.9 in. Hg.
1 BTU = 778 ft-lbf I .4335 lbf/in.
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-_ _ _ _ - i .. ,, fa, THKORY OE_t199146h_.E0WER Ph6f4T OFERATI.QU1. ELI!J.DSu_At]T! PAGE
~ niEhl100YtMMJES . I QUESTIOlJ b.01 (1.00) { Jn order to roaintain a 200 degrees F subcooling margin in the RCG when I' C3 pre s t,u re Jc reduced to b30 pr}g, enlculata what, the steam generaror { pressure must be adjusted to.
Show all work I QUEATIOlJ b.02 (2.00) Given that the reactor has been operatiner f or 1 week continuour,3 y at l o o's power at titue 0 ; end has the f ollowing powe r history: ! ! l 100 l % + l hx
Pwr 50 +
I
+ l 0 +... _ ___.. _.,___+_ _+___4 __ U
20 PO
b0
'/ 0
90 100 110 120 330 140 1b0 Time (Hrs) QuA11 tat.ively sketch the xenon transient from time 0 using the figure of xenen concentrat. ion versus time that is provided in the attachment.
(***** CATEG0hY 05 CotJTltJUEI) Ot; NEXT PAGE ****++ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _
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DUC51 1OfI ~ 6, OB ( l '. 00 ) btate tlie liu tial r es; once at tiie had Contral S y ts t o n e ' L o t hre i al i oni riq
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i.on ni u rr each situation 1odiv;duai1y, a, 'I t H T D-f o l l o m th an opt n ' N i h R) D f a a l u w.t t b i-short I i ti.
A-'l uuk e car d i n. rod- (:otit r ol J. o J 1 t cpoien?L d.
One Red Urivo MO uct peom aiar b r e a k r:-r npeim e.
Une RCP. (R eac t tw Coolant Pump) trips (a,aumo ' F:vci. Con t r al % s,t e:m.1: in ata cin a t t e at t ior m al /0% poucm aporaliana< or DO NOT MOVE.
lim L onnwor tu r ot h. C'f & II;, Ei l i~P Dili, lh!P lil, 6 w p l a n a t i c.n n oi: t Muirod.
UUEi-3T i DN o.U9 (1.00) i Ht.E o r F A L M -J.' u; T i ira Peat.t cr Trip Dvpse lir ern e' ' cr e glectrical'ly i n t er l oc h: d cuch that, 1+ mn.ettumpt..]o node to c3 ow a'uer. cod bvpeen br eaker whi1e FM I D - i 6 C l (* HOC},.Only t))ld t i P G l, b y p a t.5 s !st C Elist'T W313 (V 1 l4 Q p C'i f., b, tr<ti n l4 ui Bolid stato i+ob wl:60 Eiy e t c~n ( $ LIM ) wa.ll' trip Rtuctor irip byposm Erwtn A IF :tivpa w b r o M u:-r n in.L1ocud m io -oniy fr ai n 4 (f ~i p 1 Q 7 af i '.fdM * * r H C 6 $VUb
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- wd,
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h t5 2 E ()O l .Q W hi O: 1 D:s t. l. El) ' t lic Tiif E ,_w e t i a t i l e hu s.. ta uppls power ta lhe T .Lal b.
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' ' .} ., N. :. : * Y : ' Y , i .. k .. . MOESfluN '/,of (l DO) Durtng a.p/45t Gal em' 2 c ontfol1ed,ccolduwn ta made.D,'buth don't. ai n w cr, L spraf ~ pumps - weru i n miver t en t. l y.c l ear ed and tsgdad while in inode 4;
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t t o t. ) w. u pr a y pu+.p W (1,0) < I G,$ U,iI } C d 7.(S 12. W )'.
YN YYP f4,f dr N 4 (. ,, ) {.tI l (N f..' f..,l O I' k *d" '1 d (N . k, k, ' '" b' "sdy (310 h O l 4 oh' O .. (.) b I I O
a B l. s m Uconratar Iigh Level 4:'.0).
QUEB! ION' <, U3 (.1. 50 ) a.
'L1ST tlm TWO. Concl.i t i ons a n. EOF which ebqm y t > EDP-G hT-1, i.;r i t'i s). ~ , % f ot y 1 u nc. t. i ui t Status Trcea to be mon i t.ored. (2.C), b.. 1,.1 ET Um ' ol m f. OF c ond s t.'t on - t ila t r equ i r er, otn u 1 or a o g un1v, wi tre _ no i mp1 emc;n t a L i ae ) oF lhe a t a l u e.
Lroe. 1O.5) Gl3Etil.i ON ?.U4 i...m ) I n Yt 1Fr Fyi G --3, "iGmponue i o Uteam Gener at or. Lo w la vd, " the pr-oc ed u r v rofers la "offectod" S/U'.. Wnou cai.ntitulw mi otfected WU in hrmor deo u:n wi t h l iii :, pro m h o' (e a) '. k ausiIon 7.& <t.:, o ow mo s e arm m &t 43m a m.a s e n o t-be om aorsno-0,- 'no 6! 4 4 t.E (1.'i> oppe wLit o r (;na e, m. tin, .id t1 e )' .U JWi i t l'i. 7 (>6 ( < l-L n mnter umtion E, m f.. - n n< uu ci un in e no poi m - to x e az a c wa p wnt t.p i i i r N n! l I'L[ Ur trOm merqy O( 4 4. P s fier iI
p r O (. e c L L D ut ptH'si.a H +!i .>r t - fitLSE' iO.b) , l.
, w, wow a m wen m aa r v a ~+ i e' -_ _. _ _ - . _ _ _ - _ - - _ _ - _ _ ..
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - _ - _ _ _. _ _ _, _ _ _ _ _. _ _. _ _,,. _ _,,, _ _ _ _ _ _, _. _ - _ _ _ _. _ _ _ _ _ _ _ _ _, -. _. _ _ _ - _. _ _. _ _ _ _. - ~k Lf - , p '- b' ' k/ 'j , " " fb fgj ik k. y f
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Ill bO h1 hob 5,Oh COf) trol a., orm of the l ir.ri,ed j e t o ac i: i on s in to , .tr'ip the r edc t6r whon inutrumpot. a i r" pr 6 sure falls to, p ii g,, 3 C'. C ) {FA11 ia i i M.* b ' M d ; } } , I ) e .e Wn on. : n. ibd u il, w iv - wr vi cs watbr l wa k s in coat 41.n wnt fan coils r etpa a rec-t.0) a t tIW NRC UG OGl. l i l ed W i [:} )i f l alle hour U n i.] cM i i (T C i d Hn 't J" fm t,r { be W l[ $ k t O D '. 1.. 'I h l IWO FCdGDnD [H!r IIP 'l l i OF (l)G%i t'6lrCittiFOmO'#[fe, (i. O) . N OtiEUiiUN /. t:A ':. ou\\ i~he C mlion h t ;d o ninn t an EUP --F hHS - 1, "R.mponne to. Lone of Eocondhrv Htict-binh," s t' e t o e- 'If WR level in ai 'l out gig's 19 leau Ltian 34%, lhesi inW:dialm1v trip all RLF e end i ni t ; > 4t o kCS feed pd n i. e e d. " a.
l>%o 'i be th2 di F f vrm)c belwaun "fead and blead" .A n d ' " b l'e a d and j.C) f (Od ',
b.
l t Lt L vo bacon or rumons for requit 2og (he trip oF 1. h o RCP (1.O) .. i,1 0 F H F [ O N ?,10 Ni - Tf 'l iE cu i nLi Pfu, and )10 ( F.JRV b; xk s 1 ', n ' .m ul owtl ond pt+ ei 1a r owv ed ,e Y ' O-l] M k F u s) (fu(? E. D I-I s l atid P IC.
h t.t l n q i ( O p ' i a b l L:, I i s ti' u tt' N'il i l } ci Ji t1l0 On Ph6 Ond - f I'/ G P G(l 14 0 I be p scr r U t' M r. d 6t I IM. aiid 't' ' N '/ ut D i 'I Lo 69(i alcd pCf 5 OF mi fit [ I~. I ) el i r deaign fur,ct;toi .,d t her e f cm e, su a vpc r obl e.
(O. 30 ) , .h ,.! )
, s t l1 RUE or Fra_BE; un an emc r u s :n t v d.nletion fr om ft iuil t a r E@w.c.11 1 f ci l 10: 0a you m G rt c.<L.1r h ) a ta'natify t. h u NRt; pr A w to tim aeviatlun.
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aE s hm . a .A s y .-. lO O p f ? r a b i H ' G t. d t: M G, ) i the l W C h ri i C.21 Sp rec 1 f 2 C Jt k i Of r_i Or t.h th I n GLW V i C fd. lnGpCCil uf t IF OQF A iO fj O C ' S hDL f D Q U ll' e. D O y, E p O C i'f i C Sj t.lF V i? i } l a f t C O j
.D G k. fiQ = I1a b) )
l ! i: 1 i-t o +.eis,ur o t. t i s t this t oqu i r n:>rneilt iu j b.
WI s tw +- r n;>or n.) h 1111. / temp l e t e d' .(0.507 s
OUEB1JON .t J .( .D0) . I r%:r E I - 1 - zi.18 ( !. o ?.,s of Coiitrai Air).
9 t.c t Uti ido. .J and W N..m i i 2 e r y F e :. taw a L. r r f ' tut p s, " - _"5iARi E t op li ~ ,1
.- _1 _. _ _. _ , _ Olds T 1hW 7.14 (.50) Whil e per f ormi ty) 16 radioaci a ve Uawour r e i t a w.3 .t h e ' R47 A. i 21 RM
, Decay i,a n i ) monator h a :3 a valid alarm, tist the It1MEDTA'IE actien otep (n ) requ1 red 1 i. eny, by ps+ genc y inst r uc ti orie for d wo or -: ti.f i n g / 6 n kr g 1 J i n g
w q d ). O (YW'n t. ( O. Ils I.
DUlED I G j - /. '.l b ( 1. a ) Eer Ob ?i"-1.,,1 ' aci. c r m.d on t F' u m " Dp er w i. 3 c t i ), binlE m n:i frer to nat, a ficac t or Coo l m 1.
Fu.op /RCP< wy im w tw i ud ra each o* the i c. ) 1 n o i m ~~m_ m__ m_ m s_ m _o m _ -m _ d.x m. _ c os 4 d ) L i uti incividualiv.)
Limit au nec to J 1/ iR T or NJr cTAPI.
'l, j-i l" I' pt E*.
- U.'
41' d. ' p t:,, la ' - L \\)C : prnssuce 1.
pr,4 y ' " ' . I'M eM I i Tsin'7!itdi .s t. Q i!, i di QQN ii r ^ .. 4, '.e a ! ' 1OmkG? t t 3 Cn / g p la ^ lM 4 Fara,(;a1 ; n e. 0 - at tKW p < i c s e o :.. t ia. i +r ' m . ( A.,- ) g..e g ': lq, y r ;p f (t;p : g (: / -x:cg j -
_ - _ - _ - _ -- -- ...._.
.a - p. b) b (b et.
E l.i..... ...._......_...1..I.
....L. J. 11,1.1. )... 10. NB >%~ 1:
UUESTICM-G;6) .( 1. 00 ) - L ' J " [ hlI$ [.% I Oi on ) 6d k[e St ll } 5. di r bI h.I b_I. n,J h C N hI ~
$ yk n F't.
\\f h b (/ ' I o k f..,,$ [3 h .mtp l % f r om both bortc A..t d M er m;ps L.aol 0 and t; h e baron i o j et t 1 o'1 l' a n i: reviMJed th at t.b e b or os i.c on c e.m t r is t l ut na i n c l.J t hrw t % h welm 16,900 ppm.
(.181 k WG) To'Ci rfl1 C d l Ep0Cif1 Cat,Lun0 LCO'h Vdli c h woul ci reqttare carrective M t i ur u4 ( Oc t.1 < in 13 L o i E:n.o h l ro,L 'v q u 1 r e l 's (l.O) .
CUE.3T}CN O Oi.
('d. O h > s
~ Dury i ng patct a i en Unit 1 c t t wJ y +ta t e pnwar ope stians 01.
SO., c a,2, t..u n me n t u u,y 1 s t. - leakage rate wau noted to be 1, apm, pru morister' . lOVU1 1h
- . t a l> d P g. aM i d thDFC hsU b O l'n MO inCreebe in Chm OliiG I!DW Dr fRb
.
h) d h, t f U[). ' , a.- l. l!R the LCU/s M n ci, Wuuld t ddr es, t!) ( e ob e, ar v a t i be i. ( j 0) l - ' b.. LIGl the pr oc eciure '.or inwtrurtion'which Hao1d ,) d d.r i 7 - w th.i e ob 6a v a li t in. ( 1 O) QUE9]1CN' 9 na M N),
Uh.1 1 e LOitm y4a r eaairi og 1 W M; (che giig hender etop velw>, it 49 ( cliarg i ng atop val 9e) un relied u p.[A i ta be Li s e v l schni cul ip et i -f 1 c at i on coni e iiunent i E.c,1 e t ] u n -/ a '! v( r ecp ci e em (il +. (ICV 69 i.ai i c d the Type C ieak i
t i. 1, v tWW() t ) , N Ylf f > C i'l [ ! (, d. f. ) h.Y $ f "A { [[ k. # Cn9 ) 51- ) k '! 4'.' ) C k it'(I' Q 1 l I t_I 'r k_4 3 () M - )f..) U ? r' i
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- 1
..N , C e:i f i s: al3 cni, 3,(iu i i o '. ) at facted ly thr cond)tlan, ai i fNW m,d i ifNtdi, a; ciwgcibEd.
. (1 0) ! L, > % "i i iir Ivp A, l u r,0: l', mid i s. p e (1 i e214 l n 3 t. u i.; n tver er al i.Wom). 1 1,, U ) ! r } :. (*ux> xm o u., , i. u n 3, m D a: M P,, W.- , .
- 1 4 e i i
. _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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L 1, r11.1 A T.. i G N S fME
- ...... - ~ - - -~ - -- ,,. ) i
. puun na a na < 50,
o . < 1-
04:11 1 f14 it pakt h41 mn Uf 51 L 2 c,t. der i U fi l in riOd GI,;,, RDd d$fG te.'s f u u r i d y WJ tIi),ri eno no-o4 na w u on, en w am.m o na +cc. um youp am m 1namauam
by greater ihm + 12 s t up tt.
( tn h.er rods-genup dawnd m e 16 steps).
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. .- ' ,,. 2, k, ,,{- ,- f.
_, t m mt., ? whtch tequit.e ac L i cn > in th.io ciw ivat ir. t Q. b) i n.' n ,, . ' ' b e r ..&
HucfontI!y, (hw i ing. r'ou t i i m ptvet vper 11 i ou., ci ba l e,o. rpa l p men t opor ator, ceni t r i f ugal chm gi n'y pump ( Un, t. 2)4 ' wh)le a l t (-Arv :. n g to L y; No, a i e uid vk r t m i t 1 v d o-Un c r g 12 ed the c t.f i f r o) pauer f rir Nc.
12 c en t.r i f ug a l C ('i v3 r t.j l fi g p u h p., IQ.
I1 C h 4tt' O il't() Li t.'.M p WG3 i n Q(ie.thl U 45 h l,hi 3 t. i t,1 C. II)E t eagi sig cr r i n-w.; n o t= tot r m ta;d. '2 What Lao T oc h r. i c ki ?pec i -f a c a l. j on ' qui r unen t o ar te a f f ec t ed'. (2.0) r- .0UEJ1 ION U.06 (1.Ov) LIST 'I W U 1( l-1 s -ai por, annul oh.;> tou r s u b u t.1 t u t e c on t i ru.tou u c o ce n w b y b'ad i d k 1 Gi's F+ o l.ec t 1 on j > ur u.at iric!1 iil 1aeu of ern t6dF ior s i t.ia t i o n ra r equiririq .. -d aned a 4, t e acc tc r, t ri t o a r adi ol ogi c u'! ] y c o n t r o f 't e d a r.e a - (1,U> . A , ,., t ,- s ..$ ~. - Unnt ar e t 4 u-a r t.c monra mo ed uppui 1imitc 4 or +w c; c. r i c v dce 4 or t Im i U } I U Vii f' Q b 3 l '.I Ji l 1 Oli t t i .h. It) G ilv P c t,. ha i !On e?Q u i p h *GI ! D.
ld a nt v i,' ecA 1,1 f C - ( *., N p i u E m.fli h N2,b Y k OII b. iib k1. b ') . v trici v.ithnij t. n ei 3 W-f a e d L IEn W o. 'i Wi : L O rw i i t 1 ;v, !. d.i L h mmt im < .t : h 111 01* r a ' l l i.t l l u i WPn !. i c e ths H Bi ii x ; si Fe c t t., , 11 h um, n. (i.
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i l
- Ul;E S I 1 C?-l U.O?
I 2. M )'. e CM t a) n L e t H g,,d fpparulus bei:ome a t.t r tgu i t l y n s-ended s ur <oryJce vo i d ' t h e.
por on o,nnad an t h u ' ' L ei g As in L i ng. i n ' the Racl:iiw and can not be r t.-,a L1mti. ,ri. L1Fi i otir of i.ho'peupis by t.itle wl.o haw 1.he.ignature' authority - or pw mi t a os,, l o au 'c h t.r 12 e tho tbg reinoval.
( 1. i.) ) b, Whal o :, e a :w t-- by the c ogn i z im l. departaent tnu s t tw q a v e n - ('.I'W O a.i s t.t 4 : t.a ) i ) prior t. o au ll mr i ; i nq tap r umaml " (3.0) ! '!MERTIGN B.10 '1 :t. CH.) 'e Wi n g t iWO 1 (u t i yl dtt.tl' Wi l l ~:. i q u sii f i d d.- t t t? t, i m PO L t.
ReiK.LW f f'i p / E vi et - in lett.i on Rep or L (1.O) ) l ' [J.,.i}j r(T } (_ilj {, ') } ( j, Q ;.1 ) WhaL i-ihe b u.h c; i or' r eq u1 r ii >q o n.1 - c a n.
ran i t r A f u r.; a l t narq: no pump ta be .oporauJu tn Mode a -- i?CC col d 1og ' t il do(pw:2 i: (1 O> i i t
- l l l l l' * f * 6 Ft y I;$ [ $. ; [ [ [ f.
M h 'r 0 4 i [I , ( * 2 -> x., -- r., r-w- *, a u, f Ji 3:,,M i : jn i ! ty a v9 w+'-***<a* <r +*; \\ - _ - _ _ _ _ _ _ _ _ - _ _ - _ _ - _. _ - - _ _ _ _ _ _ ~
_. _ .,. _ _ _ _ _. -_ __ .__- _.
l C' ' o a . b -
. 1, i l- ' . l ATTACHMENT 1 ' use to answer DUESTION 5.02 SRO Theory - Salem Given that the reactor has been operating for 1 weel' continuously at 100% power at time Of and has the following power history; i 100 ^ l % + Rn l Pwr 50 +
s + ,
0 +--- ---+---+---+---+---+--- -
10
30
50
70
90 100 110 120 130 140 150 Time (Hrs) i l
Qualitatively sketch the,<enon transient from time 0 using the figure of xenon concentration versus time below.
+
+ + Xe + Conc + + i + + + o 4 _ _ _ 4 _ _ _ 4. _ _ _ 4 _ _ _. 4 _ _ _ + _ _ _. 4 _ _ _ 4 _ _ _ + _ _ _ 4. _ _ _.t _ _ + _ _ _ + _ _ _ 4 _ _ _ 4. _ _ _ + - -
10
30
50
70
90 100 110 120 130 140 150 Time (Hrs)
i
l -- - - - - -- - - -
_.
__.. _ - _ - - _ _ _ - _ _ _ -. - - - _ .
1
.- , l l l i '[ ,( l T,, H. am.,, u. n v...i e. n...t. c. s, .3
- .
',,... . 7 ._ %4. ;; *. ],,, . .,... ... ~,.
. . , I
l ' ptstjERO U4L Erl I V.' - 0 7 / Oi / :l '-> - RE I D l t iWiR. T.,
I i 5e e ' $ lq le 3 e S6 p:ia Ii t ? b l I LV.} 5 * ' ndu Ab'pui to !W D p ; 2 g S1o ptto Lu _M:, pt3 , UN1 rug c ia.v.4 L ed, l. a. m tabie ftnd that at 610 p zia . 1. h n t oinp t, n t u r > r t-9 2..;U t or - :' & cp w F L O. '"; p t :1 F a rid 4 t w,a t i e n t onp ar a t.ur p oose in #l / G RCS temp - RC3 isub c o ol l rig , - 4138 - 2u0 wet 4 or ~ ' deare> F LO.2Sptj llF il'q > c.4 L Lt l' it 'i G d 6 L OWn l' d b } V i, C l i t? C Ot~ V elspurirj i r n q p t Er G':!.U r" ( ' t O l'" , LiUprees F its b / Ci.i - S t> 4 tr - Il p c, t #4 LO. 5 ot3 , -' hi!Flif G N U Steam ~l e ti t es t.$@ 2 !. N10 h hi I ( ! ., ( h N ' I3 ) . _ _ _ _ _ _ _ _ _ _ _... _ _ _ _ _ _ _...
- _ _ _ _ _ - . . ~ * h.___IHEQ87_OE..NUCJJAJ3..EOWE8_ELAUI_QEEILAIJOth_FLUIDh_.6dD PAGE
THERMODYL1h0]CS . ' ANSWERS -- SALEM 1&C-87/06/19-REIDINGER, T.
ANSWER b.02 (2.00)
2
4
4 Xe + Conc
3 ' + +
g +
+---4---4---+- -+---+---+---+---+---+---+---+---+---4---+ -
10
30
50
70
90 100 110 120 130 140 150 ' Time (Hrs) . Notes - the following statemento are not required for full credit, but are to be used as a grading tool to evaluate the sketch: (1), Rapid increase of Xe concentrat, ion.
(2). Maximum Xe concentration is obtained 9 + 1 hours after shutdown.
(3). Dip of Xe during startup; and steady state Xe concentration at, b0% < steady state Xe concentration at 100%. Xe concentration peak (4). Xe concent. ration peak f rom trip at SQL < from trip at 100%. (b). Xe contentrat. ion is approximately nero 50 to SQ hours after
shut.down l j [0.4 p t. s for each qualitative change indicated on the sketch above] FWFERENCE l'SE& G. Hoae t o r Theory Handout., pg. 231 of Text 3-Curves, kxth - TF 39.2, 3, 4, b, &6 0 010 0 01.M -i Da1010Kb26 (KA'S) l i l l l l l , L--_________
_ -. _ _ - _ _ _ _ _ _.. _ _ - -. _. - - -_ , 3.
-. [.: I.
O...-. O l!i.:O.~R Y.. O.. F.. T. 4L.E l E AR.. 1.._(? %~ f.i._?. L. t e.N._ l...'...D.. i'.'t:' re r_. I.._I (R.1,.. F L.. U.. I.D.. S_.., I.d..) D.
PfeE
g -. . . _.... - .. _ -- . ' .. , _ ., m .. , '* ! I...
- {
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(4 % 0. 5 (:ac.ii) ' h E F fif-d; N 1 PEE %.,' LP Uo.: Md/ 364-145~ u3-iff f f' J9 00, Re v. O, did 4/9/ba, pyn, 11~ :12, 19 %GN.1 % ...(Kn B) ANMER U. M t 1., O m
i n.
wum w a paint,
ti ; F /iL SE L O. ', pca rit ] L _. R F.F E R E N G !. PCELU, L P Fio.
'# ~ 14th US ~ Oi, deled 04/ lb/EA paypr, 6 d 4.
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