ML20236C335

Exam Rept 50-440/OL-87-01 on 870602-11.Exam Results:All Four Senior Reactor Operator Candidates & Eight Reactor Operator Candidates Passed Exams.Exam & Answer Key Encl

ML20236C335
Person / Time
Site:	Perry
Issue date:	07/22/1987
From:	Bishop M, Bjorgen J, Burdick T, Clark F, Mark Daniels, Hare E, Dave Hills, Mcghee J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20236C328	List: ML20236C324 ML20236C335
References
50-440-OL-87-01, 50-440-OL-87-1, NUDOCS 8707300019
Download: ML20236C335 (173)

Text

{{#Wiki_filter:__ ..t t / 'U.S. NUCLEAR REGULATORY COMMISSION. .l REGION III I Report No. ~ 50 440/0L-87-01 .i 0 3::ket No. 440 License No..NPF-58 The. Cleveland 'lectric Illuminating' Company-Licensee: E Post Office Box 5000 Cleveland, OH 44101 . Facility Name: Perry Nuclear Power Station Examination Administered At: Perry Nuclear Power Station-t. ' Examination Conducted: June-2-11,,1987 f k h-7/2N7 Examiners: D. Hills Date-f; YY ' j6% 7/Z. 7-l97 J..Bjorgen -Date W, h% 7/2 T f7 F. Clark Date go..d h E. Hare g/ pals 7 Dat %.//dLp 7/2 tf97 \\ M. Bishop. Date i f. ft 7lZ.1/P7 J. McGhee Date $, Y f 7/? L ?Y .M. aniels Date $~ p/g 2/77 I . Approved By: T. M..Burdick, Chief Operating Licensing Section Date i j[k Skock Ob0 7 V 3

1 I i Examination Summary Examination administered on June 2-11, 1987 (Report No 50-440/0L-87-01) ] Written, oral, and simulator examinations were administered to four Senior Reactor Operator (SRO) candidates and eight (8) Reactor Operator (RO) candidates. Results: Four SR0 candidates and eight'R0 candidates-passed these examinations. I 1 i l [ l 2 i __--___-_________---____________D

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F REPORT-DETAILS 1 1. Examiners D. Hills, NRC Region'III, Chief Examiner J. Bjorgen,-NRC Region III -E._ Clark, NRC Region III p -E. Hare, NRC Region III M.' Bishop, INEL. 1 'J. McGhee, INEL M. Daniels, Sonalysts 2. Exit. Meeting i At the conclusion of the examinations, an exit meeting was. held. ~1 The following personnel attended this meeting. 1 Facility Representatives R .I F. Stead, Manager, Perry Plant Technical Department M.' Lyster,, Manager, Perry. Plant 0perations Department R..Stratman,. General Supervisor, Operations R..Tadych, General Supervisor',. Training

D.'Igyarto, Unit Supervisor, Operator Training C. Persson, License Training Instructor F. Kearney, License-Training Instructor

'NRC Representatives .D. Hills, Chief Operator Licensing Examiner, NRC Region III y E. Hare, Operating Licensing Examiner,-NRC Region III. i G.~0'Dwyer,. Perry NRC. Resident Inspector. M. Bishop,.0perating Licensing Examiner, INEL J. McGhee, Operating' Licensing Examiner, INEL 1 During this meeting, the examiners noted that no generic training 3 deficiencies'were' identified during the' operating examinations. j The examiners did however note. numerous problems with the simulator i itself. Although these problems did not seriously impact the examinations, they did prove to be time-consuming and a general 1 nuisance. l - 3.- Examination Review Specific facility comments concerning written examination questions, followed by the NRC response, are enumerated in Attachments 1 and 2. 1 3

1 ATTACHMENT 1 RESPONSE TO SENIOR REACTOR OPERATOR WRITTEN EXAMINATION COMMENTS Question 5.07 Comment: Is " ERROR CARRIED FORWARD" justification for incorrect response? NRC Response: An' error occurring earlier in an answer is not carried through the remaining portion of that. answer for the purposes of grading. Grading instead concentrates on the use of correct methods following the error. Thus, credit can be lost only for the error itself. Question 5.15 Comment: As recirculation flow is increased, Actual Power also increases. CPR = CP/ ACTUAL PWR. As actual power increases, CPR decreases. This answer should also be acceptable. NRC Response: CPR is dependent upon critical power as well as actual bundle power..Therefore without indicating how critical power changes then the change in CPR is not fully explained. (CPR.may increase or decrease depending upon direction and/or magnitude of critical power change.) Partial credit was given for knowing actual bundle power increases. However, full credit also requires . indicating how and why critical power changes. Question 6.05 i Comment: If the Rx is scrammed manually and the RPV water level remains above L-3 (177.7 inches), then the MLC would' attempt to maintain level at 196 inches. Therefore, based on information provided by the examiner during the exam or assumptions made by the ] candidate either Answer a or d is correct. There appears to be insufficient information provided to reject Answer a. NRC Response: Agree. Original documentation suppled by the facility was unclear about the RPV L3 water level interlock. The answer l depends on whether RPV water level reaches the L3 setpoint. [ Therefore, either Answer a or d will be accepted. k

y l'; ATTACHMENT 1 2 I i Question 6.12 Part b l Comment: Should include the times the bypass valves are used for plant I cooldown following turbine removal from service maintaining i hot standby. NRC Response: Agree. Question is worded such that any reasonable answer l is acceptable. I Question 7.05 Part a i Comment: Answer key -should not include Rx Pressure <920 psig since the question makes the' assumption that you are operating at 95%. NRC Response: Agree. This part of the answer is deleted and entire point value is awarded for first part of answer only. ) Question 7.05 Part c Comment: Add the following methods to achieve a scram signal. j Deenergize RPS bus by opening power supply breakers. Insert an APRM IN0P signal by opening ATWS UPS breakers. NRC Response: Agree. There are also acceptable methods. I Question 7.09 i i l j l Comment: Answer should read "... will cause direct pressurization l of the containment due to bypassing the Suppression Pool." h t' l NRC Response: Answer key is correct. Steam will still be directed to suppression pool space but above the suppression pool water i level. Since the suppression pool air space is open directly l l to the containment air space, pressurization of the suppression l pool air space corresponds to the containment air space. Therefore, credit is given for indicating that this suppression pool level is below the top of the SRV discharge and that this could present a containment challenge. l t l' t

ATTACHMENT 1 3-Question 7.10 Comment:

The LOOP and manual starts for two to three minutes phrase should not be required for full credit since it was not specifically asked for in the question. NRC Response: -Agree. Intent of question is to just test awareness of availability of diesel upon diesel shutdown. Other information is not required for full credit. Question 8.01 a and b Comment: A possible response to Part b could be No Additional Actions. This response would be valid if the candidate indicated in Part a of this question that he would enter the action statement upon the discovery in Part a. 1here is no additional actions necessary now because both divisions are inoperable. NRC Response: Agree. If action statement is entered in Part a, credit will be given for "No Additional Actions" in Part b. Question 8.02 Comment: Overall, this is a scenario that would require the control room supervision to use the PAP prior to making this difficult decision. In the future, consideration should be given to providing the candidate with the reference material. NRC Response: An SR0 is expected to know overtime limitations and the rules affecting these limitations. Requirements for this knowledge can be supported by appropriate K/As. Question 8.06 Part b Comment: More indications of annulus status exist in the Control Room in addition to the " low" alarm listed. Other possible answers that should be considered are: Annulus Differential Pressure A (B) Controller Indication AEGTS Fan Status Lights AEGTS Exhaust / Recirculation Damper Position "AEGTS Fan A (B) Flow Low" Alarm

y.- f,; e i[ k. fATTACHMENT11 4

NRC" Response: (Partially agree. Will accept annulus differential Pre's'sure A4

-(B) contro11er' indication and AEGTS. Exhaust / Recirculation Damper - ' Position. However, AEGTS Fan status light ~and "AEGTS Fan =A-(B) Flow Low" alarm ~are not. acceptable-since they would not .necessarily; indicate any. problem with low annulus differential ~ pressure.due-.to an open door. ' Question 8.06'Pa'rt d-Comment: This question should be delet'ed..-It; incorrectly states that!. PAP-0220 has been revised and therefore the license-candidate should be aware of.the revision, In fact, PAP-0220 has not been revised as of exam'date. Furthermore, LER 86-076 states. that PAR-0220 will be revised. NRC: Response: The event in question occurred November 3; 1986..LER 86-076, issued November 28, 1986, indicated PAP-0220'would be revised L 'to require witten authorization from the. control room unit. supervisor prior'to posting open ar.y containment-access portal. Revision 1 to LER 86-076, issued April 3, 1986, changed thisi to apply'only to posting open of-a secondary containment access portal. : PAP-0220 was not providedLto the examiners with'the. s ~ ' original 3examinationLmaterials'and therefore this question was-based-upon the LER alone. The ine'xplicable delay in implementing the corrective actions has been referred to the'NRC resident- -inspector's office.at the Perry Plant for evaluation. Since .the' procedure has:not yet been changed, this questio'n was deleted.

Question '8. 07 :

Comment: The Perry Hot License Class received training on LER 86-001 through 86-050 as well as LER's dealing with significant plant events. LER 8711 was recently covered in Perry Requalification Training and was not delivered to the Perry License Class. Furthermore, this LER was'a result'of a QA audit four months after the fact. This indicates that the Control Room Unit supervisor using a copy of Technical Specifications missed Action Statement 3.3.7.9 No. 110. Again this was (is) a good thinking type question, but the candidate.should be provided with a copy of T.S. 3.3.7.9. We request that for these reasons, this question be deleted. NRC Response: The purpose of the question was to test familiarity with i LER 87-11. As this LER dealt entirely with violation of the i Technical Specification Action Statement, it is not unreasonable for the candidate to be able to answer the question without t \\, i N

,:t . c.~. ATTACHMENT.1 5, 1.. being given a copy.of this Technical Specificat. ion. As the date of.this LER was March 25, 1987,. sufficient time existed for'.it to be presented.to the licensee class. Furthermore, LER 86-046 dealt with violation of this same Technical Specification' Action Statement. Therefore, the question remains'in the exam. Question 8.11 Pa'rt f .. Comment: Since a " qualifier" was placed at the end of the statement, ("if deemed appropriate"), the candidate may feel that TRUE is.the correct: response. Both 'T and F should be accepted. NRC Response: 'This. comment may be valid for an RO examination since it would imply that the fire brigade member is being given an order by the ' shift supervisor which is contrary to the plant administrative - procedures. However,'this was an SRO examination and as such the candidates were. tested to the level of responsibility of ) the senior licensed shift position (i.e., shift supervisor). i Therefore, the. candidates should'be aware of their authority in this position per plant administrative procedures in regards-to this occurrence. l I 1 l l

l ATTACHMENT 2 RESPONSE TO REACTOR OPERATOR' WRITTEN EXAMINATION COMMENTS Question 1.11 [ Comment: Part b) Could be BOTTOM' LOADED per reference listed in exam O_R EVENLY DISTRIBUTED per INTRODUCTION TO NUCLEAR RX OPERATIONS, Page 6-2. Part c) Recommend deleted Part c due to conflict between references. Recommend Part a) and b) be. revalued-to 0.75 points each. NRC Response: Comment not accepted.- Training Material in Introduction to Nuclear Reactor Operations Pages 6-2 is.in error. The training per Learning Objective OT-3036-JH-00 should have explained the additional rods. Question 2.02 Comment: Other auto actions that occur under these conditicas are: 1) Isolation of Rx Sample Valves 2) Tripping of Mechanical Vacuum Pumps The list of possible answers should be expanded to include these two. Recommend changing either the question to require three out of five possible answers or change point value to 0.30 each. Reference SDM D17A, Page 27 j Reference SDM B21H, Page 59 NRC Response: Accept comment. The additional auto actions are included in the answer, point value changed to any three at 0.5 each. Question 2.03 Comment: Answer ke,v in error. Items a and c are the same key. Recommend either require only two answers or accept LOCAL MANUAL operation of valve operator. Item b should not require MCC identifier for full credit. t Reference SDM C41, Page 10 NRC Response: Accept comment. Two required at 0.75 each and local manual acceptable as one answer. MCC identifier not required.

ATTACHMENT 2 2 Question 2.04 Comment: The setpoint of 8.35 psig stated in answer key was obtained from SDM E12. However, Perry Technical Specifications lists this as <8.35 psig. For this reason, answers of between 8.0 and 8.35 psig should be accepted. Reference 3/4.3.9 Plant Actuation Instrumentation NRC Response: Accept comment. Tolerance given for 8.0 to 8.35 psig. Question 2.05 Comment: a) Level 1 is equivalent to 16.5 inches, both are acceptable, b.4) Is 577.7 psig required for full credit? S0I E12, Revision 4, Section 4.3 states 600 psig. The following items should be added to the list of possible items obtained from S0I E12 Sections 4.3 and 5.1. Minimum Flow Valve closes LPCS Support Systems Start LPCS Pump amps LPCS Pump flow NRC Response: 2.05a Accept comment. Eitner Level 1 of 16.5 inches is acceptable. 2.05b Accept comment if indeed Revision 4 of $01 E/2 Section 4.3 states 600 psig. Revision 3 which was sent with the reference materials does not. Question 2.09 Comment: a, b, and c a fifth answer should be accepted: l a Manual using keylock switch b Switch taken to open c Minimize local suppression pool heating during valve operation Reference S0I B21, Revision 4, Section 7.3 b) ADS mode is initiated by low RPV water level only. No DW pressure input into the ADS logic. ) i _ __ _ _ _ -_m

y i l i ' ATTACHMENT 2 3 NRC Response: Accept comment. Question changed to four (4) of the J five (5) modes of operation. ] 4 Manual initiation is also accepted. Drywell pressure is illuminated as an introductory signal. l Question 2.10 j Comment: Technical Specifications 3/4.3.3, ECCS Actuation Instrumentation Setpoints, lists Loss of Voltage as 3010 VAC and Degraded Voltage as 3800 VAC. These values are 75% and 95% of rated voltage (4000 VAC). These values should be acceptable for setpoints, b.2 The time of one second stated in the answe' key I is incorrect. Time delay is 15 seconds. ? I NRC Response: Accept comment. Listed voltage, or 2 percentage of voltage is acceptable. The five (5) was left off-the answer when printed. The correct answer is "15 seconds." Question 2.13 Comment: Item g. is not an actual breaker permissive but rather a result of breaker' operation. This should not be required for full credit since the operator will meet this condition upon breaker operation. NRC Response: Do not accept comment. R43 pp 12 lists closing the output breaker as a permissive for breaker closure from the control room. \\ Question 3.02 Comment: a. The setpoint for low SWC system pressure of 13 psig is an old setpoint. Other possible setpoints that this license class was made aware of were: 50.5 psig Reference S0I N43, Revision 3, pp 1 0_R 37 psig Reference ARI H13-P680-8 B6 1 Any of these three setpoints should be accepted. The setpoint of 81 C corresponds to 178 F and should be accepted.

I q .g ,y ATTACHMENT'2- '4 'SDM N32/C85 s'tates that the runback must take generator-c. g armature current to below 17% in 3.5 minutes. Both 17% N and-25%.should be acceptable. ~ Reference.SDM N32/C85, Revision 1, Page 79. '. NRC. Response: 3.02a . Accept comment. S0I NA3 was not included in ~ reference material, but will accept 50.5 psig and 37 psig'as setpoints. 3.02c Accept comment. 17% or 25% is acceptable. .y Question 3.03-Comment: ~0perators are not required to memorize specific valve numbers. ~ Items a., b., and c. should allow combinations of 2 and 3 or .3.and 5 since all three are containment isolation valves. Disregard.this. comment if-the examiner provided specific valve names during the exam. NRC' Response: -Accept comment. The valves were identified during the examination, seemed to present no problem. Question 3.04 Comment: Question is poorly worded and may result in a variety of responses. Other. responses in addition to'those listed in the answer' key must be: CRDM Servicing Platform properly aligned Area below IRM's-are clear from obstructions Power is available to retract mechanism IRM is selected Reference S0I C51 (IRM) Revision 3, Pages 1 and 3. NRC Response: Comment noted. Candidates had no problem identifying what was required. l Question 3.10 Comment: Response by candidate will be based on the position of the off gas' TREAT-AUT0-BYPASS switch.

-f ' , ATTACHMENT 2' 5 TREAT-No automatic actions AUTO-Off gas systems aligns to the treat mode BYPASS -No automatic' action Disregard' this comment.if additional information was provided to candidates during the exam. NRC Response: tComment not accepted. During the examination,:the highest -level.of radiation was specified. Question 3.11 Comment: .The wor' ding:of Choice b. "on the Motor Control Centers (MCC's)" may cause the candidate to discount this possible choice because there are no RSTS located on the.MCC's. This could' lead him to respond to.d because it is'true'that'all three position. control. switches are.ieft in the NORM position. For this reason, both. b and d should be accepted. j NRC Response: Comment.noted. The candidates had no problem with a selection between "b" and "d." 1 Those who'had problems: selected "c" which was not a correct response.' I Question 3.14' Comment: Could Part a. be two separate answers (due) to the placement-of the word OR? j 'NRC Response: There seems to be no confusion. Either response to 3.14a is correct.~ However, they will not be. accepted as seperate-answers since they both deal with the same function (i.e., Limit Steam line flow). i Question 3.15 Comment: Are setpoints required in Part b. for full credit? j NRC Response: No. Setpoints not required for full credit. They ware i listed to define the pressures and levels. 1

' ATTACHMENT 2. 6 Question 4'.05b Comment: Rx cooldown can be accomplished by: 1. Steam bypass valves at pressure greater than 100 psig I with the main condenser available. 2. SRV's at pressures' greater than 100 psig with the-i main condenser not available. I 3. Initiation of shutdown cooling at pressures less than I 100 psig by throttling RHR Rx inlet and bypass vaWes to limit CDR. Since no initial plant conditions were stated, any of the three should be accepted for full credit. Reference I0I-13, Revision 1, Pages 5, 7, and 9 l NRC Response: Accept comment. Answers 2 or 3 are acceptable if the candidate specifies the plant conditions. l Questior 4.08a j Comment: a. New RPV level band has been developed since the mailing of this reference. A band of 192 to 200 inches should also be given full credit. l Reference ONI N27, Revision 3, Page 2 l t NRC Response: Accept comment. Based on Revision 3 of the ONI, either 197 to 205 or 192 to 200 inches is acceptable. l l Question 4.11 i Comment: a. Question is poorly written. It leads off by putting the candidate's mind in Containment Temperature Control (PEI D23-1) then jumps into Containment and Drywell Pressure Control (PEI D23-2). The answer for Part a. I given in the answer key is incorrect for BOTH PEI's. i Possible correct response are: Containment Temperature greater than 90 F or Drywell Pressure greater than 1.68 psig depending on the PEI chosen by candidate. l l ____-________________1

7 i 1 ' ATTACHMENTS 2 / 7 b. ' Answer key is' Incorrect and'does.not illustrate all required actions'used to control containment press'ure (temperature). The answer key'should consider the following possible answers: 1). : Restore Containment Heat Removal Systems 2). Use of Containment Sprays 3). Use of. Containment Venting: Items 1) and 2) are common to both PEI's, Item 3) would: be given-in response to containment pressure control. Reference PEI D23-1-and D23-2 .NRC Response: Accept comment. Credit will be given~for the. candidates . response for either PEI D23-1 or PEI D23-2. Correct responses based on the comments will be' acceptable. Question 4.14 ) Comment: Item c is-incorrect on answer key. The correct answer is-No. 4, Mechanical Foreign Device. 'NRC' Response: Accept comment. Answer key changed. i Question'4.15 ' Comment: Additional immediate action found in PEI B13, Section 3.0 is " execute 3.1 (Power Control).3.2 (Pressure Control) and 3.3 I (Level Control) concurrently. Reference PEI B13, Page 4 NRC Response: -Accept comment. Question changed to two (2) out of four.(4) immediate actions. 3.1, 3.2, and 3.3 will be accepted as one (1) of the two (2) answers. i i j. 1 I I e

g._. l i /. U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _ P E B B Y,,, l i g _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ q REACTOR TYPE: gWB-9g6_________________ DATE ADMINISTERED: _82496492__ _____________ EXAMINER: _gggBGENz_yz_,,___________ C ID AT : INSIBUCIIgug_Ig_geggIgelgi ky Use separate' paper for the answeis. Write answe.rs on ont side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade. requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (d) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY I _ 2669E_ _I916L ___gCgBg___ _yeggg__ ______________geIggggy_____________ 2443 EE199-_.34T71 _ ______ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS Z% C3 _2E199__ _ M '6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 2.4. n l _E61E9._ 2&IT@ _______ 7. E'ROCEDURES - NORM AL, ABNORMAL, EMERGENCY AND RADIOLOGICAL T CONTROL ? f oo z.4 C7 .2 If?'_ M ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS /ol.sd. 14ht9_ _ Totals Final Grade All work done on this examination is my own. I have neither given not received aid. _ _.= susene emp_een _ _ een _ _ _ emma em _ _ _ _ myem. seep __mm..e _ _ em sue _ emk.Em f @. g ~ Candidate's Signature n" ~,,a -m, KAASTER CORY

1 l / j NRC RULES.AND CUIDELINES FOR LICENSE EXAMINATIONS l Durin3 the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties. 2:. 'Restroom trips.are to be limited and only one candidate at a time may leave. You must avoid s11 contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. 3. Use black ink or dark pencil gely to facilitate legible reproductions. 4. Print your name in the. blank provided on the cover sheet of the examination. 5. Fill in the date on the cover sheet of the examination (if necessary). 6. Use only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of gagh section of the answer sheet. 8. Consecutively number each answer sheet, write 'End of Category __' as appropriate, start each category on a opw page, write goly go gog side of the paper, and write 'Last Page' on the last answer sheet. 9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least thtgg lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

commonly use,d in facility litgtgtgry.

12. Use abbreviations only if they are

13. The' point value for each question is indica.ted in parentheses after the question and can be used as a guide for the depth of answer required.

i

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the gugmi0gt only.

17. You must sign the statement on the cover sheet that i ndicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed. <sm - w a

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18. When you complete your' examination, you shall:

a.

Assemble your. examination as follows:

.(1) Exam-questions on top. ) '(2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer. b. Turn in your copy of the examination and all pages used to answer the examination questions. i I c. -Turn in all scrap paper and the balance of the paper that you did f not use for answering the questions. 1 i d. Leave the examination area, as defined by the examiner. If after leavins, you are found in this area while the examination is still in pro 3ress, your license may be denied or revoked. t I 1 l i i ~ l 1 _____m_ __.__--_c.

y 2..= 5.t.__IVE981 9E_NUCLEoB_E9BEB_ELoNI_DEEB4II981_ELVIQat_68Q PAGE 2 IBEBd991HodIGS QUESTION 5.01. (1.00)- 1 PEI-B13, " Reactor Pressure Vessel Control,' Attachment 5, ' Power Control Using RPV-Level' describes the method of lowering Reactor Pressure Vessel (RPV) water level to reduce the heat generation rate. Explain how lowering RPV water level assists in reducing the heat generation rate. (1.0) QUESTION 5.02 (1.00) PEI-E12, " Suppression Pool Temperature Control,' contains a caution that Gif the RCIC, pump is taking suction from the suppression pool, then observe the RCIC Turbine Speed Limit, Figure 1.* n cowr orr passews ;- =- .en-=- -ss=a. 4aus 's = 1__ __..A.. _. _ _ %- _._= __

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I Explain why this limit is imposed and possible consequences of not meeting this 1imit. l (***** CATEGORY OS CONTINUED ON NEXT PAGE xxxx*)

1 / GUESTION 5.03 (2.50) I Choose the correct responses in each of the following statements regarding Reactor Pressure Vessel (RPV) water level indication. a. Elevated reference les temperatures will 1. (INCREASE, DECREASE) the density of water in the reference leg, resulting in a 2. (SMALLER, LARGER) sensed differential pressure and a 3. (LOWER, HIGHER) indicated level. ) b. RPV water level indications are calibrated to read 4. (MAXIMUM, MINIMUN) level when zero differential pressure is applied. c. As most RPU water level indications measure the level in the downcomen annulus, actual RPV water level is slightly 5. (BELOW, ABOVE) indicated level at rated e:oditions. QUESTION 5.04 (2.00) Explain the reasons for each of the following in regards to the attached j Figure from Perry Data Book, Tab A, PDB-A002. (Predicted Shutdown Margin versus Exposure for Cycle 1) (2.0) a a. Predicted shutdown margin ir}c t eJ/he between 0 and 0.2 GWd/t. b. Predicted shutdown margin decrease between 0.2 and 6 GHd/t. c. Predicted shutdown margin increase between 6 and 9 GWd/t. i i l s I (***** CATEGORY 05 CONTINUED ON NEXT PAGE ***rx) i

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'0,UESTION-5.05-(2.00) "A reactor.startup;is i ri p r o g r e s s ~. '.The reactor engineer has estimated that the:reactornshould so. critical at: notch 28 on a particular control rod if L theJreactor operator:reachesfthat notch at 0800..; State how each of the 'followins conditions o'r events would affect the, actual critical rod positio,n:(MORE ROD' WITHDRAWAL,'LESS ROD WITHDRAWAL, or NO SIGNIFICANT EFFECT).'. Assume that -if rua conditions changed,.the. reactor would"have been critical at notch'28 of'the indicated rod. "'a.- The, reactor has'.been shut dowri:from'eNtended full power operation for 35shours'and due to circumstances beyond the operator's. cont.rol,. w they will1not have'the indicated rod.at. notch 28 until approximately-0900. b. -Shutdown coolins-is terminated. c.

Reactor water cleanup isolates.

-d.- The reactor head vent is inadvertently closed. DUESTION 5.06 (1.00) IndicateJwhether core flod will' INCREASE,' DECREASE, or REMAIN THE SAME if p Power is reduced from 100% by control rod. insertion. EXPLAIN WHY. '(Assume recirculation flow control valve' position-remains constant.) QUESTION 5.07 (1.'00) A pressure sause in the' Auxiliary Boiler Steam Dome is suspected to be. reading improperly at'400 psis. Its calibration is out-of-date. A newly calibrated thermometer is takins readings from the same place.and is registering'456 degrees F. Indicate if the. pressure sause is-Too High, Too' Low, or'is Accurate and by how much. -Show all Work for full credit. i QUESTION-5 08 -(1.00) Describe how (INCREASE,, DECREASE, or REMAIN THE SAME) reactor power will' change lduring.the'first 15 minutes following a turbine trip from 'approximately 25% reactor power. EXPLAIN WHY. (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) e.g 4 a'S 6 6 6gr4 m k 2-_._____._._m_ _ -. _.~___

GUESTION 5.09 (1.00) Select the correct word in parenthesis for each of the following statements concerning suberitical multiplication. a. The closer the reactor gets to critical, the (SHORTER /LONCER) the l wait must be to allow the subcritical neutron density to reach equilibrium. bo Suberitical count rate is (PROPORTIONAL, INVERSELY PROPORTIONAL) to k-effective. QUESTION 5.10 (1.00) The attached pump-performance curve is for.an actual pump in a Perry Plant System. Indicate which pump this curve represents. (Give either the equipment number or the pump name.) (1.0) GUESTION 5.11 (1.00) State for which condition (a or b) the reactivity coefficient would be more negative. EXPLAIN YOUR CHOICE. a. Moderator temperature coefficient for a 75% cor. trol rod density. i b. Moderator temperature coefficient for a 25%+ control rod density. i l 4 1 (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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~n QUESTION 5.12 (1.00) The reactor scrams from full power, equilibrium Xenon conditions. Four hours later, the reactor is brought critical and power level is maintained on range (5) of the IRMs for several hours. Which one of the following statements is correct concerning control rod motion during this period? a. Rods will have to be withdrawn due to Xenon build-in. b. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of Xenon burn-out. c. Rods will.have to be inserted since Xenon will closely follow its normal decay rate. d. Rods will approximately remain as is as the Xenon establishes its equilibrium value for this power level. QUESTION 5.13 (1.50) With a recirculation flow increase at power, characterize (INCREASE, DECREASE, or REMAIN THE SAME) the effect on the final equilibrium values for the following: a. Void fraction l b. Doppler reactivity coefficient c. Feedwater enthalpy QUESTION 5.14 (1.50) l a. Explain how a ' reverse power effect" can possibly occur in response to a one-or-two notch withdrawal of a control rod. (1.0) b. Will ' reverse power effect' be more likely to occur in the withdrawal i of a deep or shallow rod? (0.5) i (***** CATEGORY b5 CONTINUED ON NEXT PAGE xxx*r> i

H$E@@QQf@@@8CS ---~~~ l l l l GUESTION 5.15 (2.00) The. reactor is operating on the power to flow map at the 100% rod pattern line at about 70% core flow. Power is increased along the rod line by further opening the recirculation flow contr'o1 valves. Indicate whether Critical Power Ratio (CPR) will INCREASE, DECREASE, or REMAIN THE SAME. EXPLAIN WHY. i OUESTION 5.16 (3 00) For each event listed below, state WHICH reactivity coefficient will respond first, WHY it responds first, and WHETHER it adds POSITIVE or NEGATIVE reactivity. a '. SRV opening at 100% power b. Rod drop from 1 0 0:.. p o w e r c. Isolation of a feedwater heater string's extraction steam at 100% power. QUESTION 5.17 (1.50) During refueling, the reactor is suberitical with a stable count rate of q 50 counts per second and k-effective 0.96. A new assembly is arj ed to l = the core and after 5 minutes the new count rate is 50 cps. What is the I new k-effective? l 1 (***** END OF CATECORY 05

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maamowmmacc000aacma00aamccacoccoca-amomeeeeeeeveeeeuwe - -mm m 1 l' QUESTION 6.01 (1.50) 1 Draw a simplified diagram of the Class 1E 4.16 KV power supplies that shows the relationship between main Perry Bus 11 and 12, Start-Up XFMR's 200-PY-D'and 100-PY-8, Interbus XFMR's LH-1-A and LH-2-A, and Buses EH11, 12, 13. Include the Division 1, 2, and 3 emergency diesel Senerators and indicate which breakers in the diagram are normally open. QUESTION 6.02 (3.00) With the plant in Condition 5 and refuelins activities in progress, a steady decrease in reactor cavity pool level is reported. They have a bundle on the move from the vessel to the fuel storage pool. a. List five systems that can be used to restore cavity water level. (1.5) b. Identify five possible leakage paths that could be causing the level loss. (1.5) OUESTION 6.03 (.50) The Low Pressure' Core Spray System (LPCS) is being taken from Standby Readiness to Secured Status in accordance with SOI-E21, ' Low Pressure Core Spray System." In conjunction with this procedure, the LPCS and RHR A WATER LEG PUMP 1E21-C002 is stopped. Other than LPCS and RHR A, what other syster is now considered i noperable? (0.5) I l l l l l (***** CATECORY 96 CONTINUED ON NEXT PAGE

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QUESTION 6.04: (2.00) ' Answer each:cf the following TRUE or FALSE concerning the Reactor Core Isolation: Cooling'(RCIC). System.- a.'

Upon-an automati'c RCIC system initiation signal, if the RCIC Pump Suppression Pool'(SP) Suction Valve.1E51-F031 is already open, then s

this valve'will automatically close and the RCIC: Pump Condensate Storage Tank (CST) Suction Valve 1E51-F010 will automatically open.. (Assume CST and SP water levels are normal.) b. 'Either RCIC' System Division 1 or Division'2 Isolation' Logic will close1the Steam' Supply Inboard Isolation Valve 1E51-F063 uponLRCIC equipment area high temperature. c. To prevent water being drawn into the exhaust line.from the suppression pool due to steam condensation, a vacuum-breaking line.is -provided to connect'the suppression pool air space tofthe RCIC ' turbine' exhaust.line, d. The RCIC Low Steam' Supply Pressura and RCIC Turbine Exhaust Diaphrasm High Pressure Isolation: signals are nct affected by the Leak Detection, System.RCIC Isolation Bypass-Switches. ' QUESTION' 6.05 (1.003 Choose which one.of the following statements correctly describes the response.of the Feedwater. Level Control System following a manual scram.- ( Pr ior'. to - the' scr am, the plant is at 100% rated thermal power, the 'Feedwater Master Level Controller is in control-(three element control) and its tapeset.is set st 196 inches.) a. The Feedwater Level Control System will attempt'to maintain level at the 196 inches tapeset setting on the Master Level Controller. b. Control will be automatically shifted to the Startup Level Controller and thus the Feedwater Level Control System will attempt to maintain .the level previously set on that tapeset. c.. The reactor feed pump turbines will runback to minimum flow due to redundant reactivity control system feedwater runback logic. 'd. The Feedwater. Level Control System will attempt to maintain a level of'220. inches and later a level of 184 inches. 1 (***** CATECORY 06 CONTINUED ON NEXT PAGE

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QUESTION 6.06 (1.00) During a plant transient from 100% rated thermal power, actual reactor water level decreases and remains near the top of the active fuel for several minutes prior to recovery. Immediately prior to this transient,.it was discovered that Narrow Range Level Transmitters LT-N095A and B had failed upscale. All other instrumentation functioned properly. -Indicate which one of the below automatic functions will NOT have actuated as a result of the transient. (Assume no operator actions.) a. Reactor Scram b.c Closure Signal to the Residual Heat Removal System Shutdown Cooling Mode Isolation Valves c. Automatic Depressurination System Actuation d. Recirculation Pump Trip from Fast to Low Speed Power Supplies e. High Pressure Core Spray Actuation QUESTION 6.07 (2.00) Your shift is performing a reactor startup. Criticality is achieved with a 120 second period at a moderator temperature of 180 degrees F. Due to a personnel error during calibration of a HPCS initiation instrument, the dPCS pump starts and the system injects to the vessel. i Assume no operator action. 1 a. At what level does this transient terminate? (0.5) j l b. Explain how the injection is terminated, i.e, what component (s) function? (0.5) l c. If a reactor scram were received during this event, what reactor 1 protection system function would initiate it? Include the parameter and setpoint. Assume a scram signal was not caused by the personnel error. (0.5) d. How would the system respond if the operator had just closed the 1E22-F015 suppression pool suction valve prior to the initiation j signal? (0.5) i i I (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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. QUESTION 6.08 (2.00) Regarding the Recirculation System pump seals: a. Failure of only the inner (number 1) pump seal is indicated by a number 2 seal pressure (INCREASE / DECREASE) and a (DECREASE / INCREASE) in staging flow. (0.8) b. Failure of only the outer (number 2) seal is indicated by the number 2 seal pressure beins (HIGHER / LOWER) than normal. (0.4) i l I c. Failure of both seals is indicated by a (HIGH/ LOW) flow alarm and L a pressure (DECREASE / INCREASE) in both seal cavities. (0.8) GUESTION 6.09 (2.00) l One of the major Design Base Accidents (DBA) at a Boiling Water Reactor is a Recirculation System suction line break. The system jet pumps provide 1 two key features that mitigate the consequences of this accident: ) Maintaining 2/3 core coverage and restricting vessel. blowdown (or draindown) rate. a. Explain when and how 2/3 core coverage is achieved and maintained. (1.0) 6. Explain how the jet pumps restrict the vessel blowdown (or draindown) l rate. (1.0) QUESTION 6.10 (1.00) l You have been asked to assist with the final containment closecut inspection. While visually inspecting the area between the drywell wall and the containment vessel, you notice the 'A' main steam line appears to be smaller than the other three. The system engineer explains that the i guard pipe must be missing from the 'A' line. Explain how the missing guard pipe creates a serious operational problem. ) Neglect legal or regulatory issues. j l 1 1 i (***** CATEGORY 06 CONTIhUED ON NEXT PAGE r****) 1

=---------- ------- L' L ~ QUESTION 6.11' (1.50)' LThe Post Accident Radia' tion Monitoring System.(PARM) provides information to operators regarding radiation. levels following a Loss of Coolant . Accident.. a '. : Each plant effluentLairborne monitoring subsystem sampling unit has three redLalarm' lights.~ WHY? b. The'TSC and EOF' airborne monitoring' equipment enclosures have two sets of amber and red' lights; one set on. top and one met on the side. If the Red Light on the side of the enclosure becomes energized, whatiis the Problem? h j e.; TRUE or FALSE. h ( The. normal position'for.the Remote-Local control switch.for the Containment and"Drywel'l Radiation Monitors'(located on the microcomputer's control unit) is the REMOTE position.

0UESTION 6.12 (1.75)

' Upstream of'the Main Turbine Stop Valves and Control Valves, all four Main- .j Steam' Lines-converse to form the. equalizer manifold. a. l Identify'four components / systems that receive steam from the equalizer manifold.- (1.0) 6. Downstream of the equalizer manifold, steam goes directly to the seven bypass valves. When-are the bypass velves needed during operation and:what is their total capacity? (0.75) i GUESTION '6.13 (2.00) Regarding the Containment Atmosphere Monitoring System (CAMS): a. 'What'three containment parameters are monitored (recorded) at the Remote Shutdown Panel? (1.0) b.~ While operating at 90% power, a leaking safety relief valve causes a high drywell temperature alarm to be sensed by the closest temperature (local temp. 145 degrees F) monitor and the local suppression pool temperature (local temp. 107 degrecs F) monitor. Does.this place the plant in a Technical Specification Limiting Condition?,for Operation (LCO)? Why or Why not? (1.0) v (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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.t__uessa_e.eeee--eeeeeee-eeeeeece-wee _eeeeeeeeeeeeeem QUESTION 6.14 (2.75) a. State the three Purposes of the Residual Heat Removal System. (1.0) 6. A RHR pump discharge pressure of at least __________ psig must be obtained to permit ADS actuation. (0.25) c. State the initiation logic interlocks that must be satisfied for the Containment Spray Mode of RHR to automatically initiate. (1.5) GUESTION 6.15 (1.00) During a reactor startup under cold conditions, the operator adjusts the control rod drive pressure control valve to maintain a + 260 psid between E::P ain how this pressure differential is l CRD and reactor pressure. automatically maintained as reactor pressure increases during the ensuing startup. (Ignore operator required minor adjustments.) ( * *: x *

• END OF CATEGORY 06
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~5I51s5Is$s55_$$O $$5 I QUESTION 7.01 (3.50) 'a. Identify three conditions that would-require evacuation of the [ control room per ONI-C61, ' Evacuation of Control Room". (1.5) l b. List five immediate operator actions desired to be performed prior to evacuating the Control Room per DNI-C61. (2.0) ( l QUESTION 7.02' (2.00) Identify four responsibilities that each nuclear worker assumes to Keep j his or her personal exposure As Low As Reasonably. Achievable as outlined in PAP 0118 ' Operational ALARA Program *. (2.0) f i QUESTION 7.03 (1.50) While reviewing the Unit Operator's Log, you observe that a Containment ( Vessel Purge System isolation is received. According to Procedure PAP 0205, ' Operability of Plant Systems': l At least one of three general criteria must be met prior to overriding the isolation. What are they? (Include all three) (1.5) { } QUESTION 7.04 (3.50) Shortly after assuming the shift, the Supervising Operator informs you that the Division 1 125 Volt battery charger'has tripped, and the Division 1 trouble and low voltage alarms are present. Other personnel report that a loud noise'like an explosion was heard in the battery room area. Due to the possibility of toxic gas being present, you decide to use the guidance of the ' Confined Space Entry Procedure,' PAP 0516, for initial entry into the Battery Room. a. As the Cognizant Work Supervisor and Unit Supervisor, identify four items that you are required to ensure, excluding tagouts, prior to authorizing entry into the Battery Room per PAP 0516. (2.0) b. A confined space tag-out shall be a _______ (color) tag-out due to the ____________ concern. (1.0) cc Initial entry and atmosphere testing of the confined space will be accomplished by the or designee. (0.5) (***** CATECORY 07 CONTINUED ON NEXT PAGE

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T@@Q$9EQ9IG6E_C$$$@$E ~ ~~ v .GUESTION 7.05 (3.00) The plant isioperating at 95%'of rated power'. Instrumerit Maintenance and Electrical Maintenance are troubleshooting,a problem with-the Rod Control and;.Information System.- Each timeua rod is selected, insert.and withdrawal blocks are' received. The operatins control rod drive pump

trips.

The. backup pump does-not start after repeated attempts. .a. ~What indication (s) would require you to place the Mode Switch in Shutdown per Technica1 Specifications and ONI-C11-ir " Inability to Move Control Rods'? (1.0) 'b. If rods failed-to move when'the mode switch was placed in shutdown,- i ~ hat procedure would you enter first? Why? (1.0) w c. . List four alternate methods that' could be used to obtain a. scr am. I -(1.0) GUESTION. 7.06 (3.50) i With the, plant operatins steady. state at 80% rower. a minor transient is received. Of the' alarms present, the following clarms require a response FCV-A Motion Inhibited FCV A HPU INOP Master Cont Trip Output Rate 1 F i v >: Cont' Trip Output Rate l Rod Block APRM RCIRC Flow Hi a. Identify three plant parameters (indications) that should be checked .to pinpoint the problem. (1.5) b. What problem are the alarms indicative of? (0.5) c. Identify three immediate operator. actions that should be initiated? (1.5) (***** CATECORY 07 CONTINUED ON NEXT PAGE *****) =*TM - e reed .]

8b9$9$99196$_G90189$ QUESTION 7.07 (2.00) P pe break outside containment, Procedure ONI-N11r Following a high energy i High Energy Pipe Break Outside Containment,' requires a fast reactor shutdown in certain circumstances. a. Briefly explain the circumstances when a fast reactor shutdown is required. (1.0) b. How is a fast reactor shutdown accomplished, i.e., what two steps a're performed? (1.0) 1 i QUESTION 7.08 (1.00) I SOI-M14, ' Containment Vessel and Drywell Purge System,' contains a precaution to ensure charcoal filter temperature remains below 300 degrees F. l Choose which one of the following that describes the reason for this Precaution. i a. To prevent the airborne release of gaseous radioactive iodine. b. To prevent destadation of charcoal filter efficiency, c. To prevent humidity buildup in the charcoal filter. d. To prevent spontaneous combustion of the charcoal filter. 1 GUESTION 7.09 (1.00), ' Emergency RPV Depressurination,' of PEI-B13, ' Reactor Pressure Vessel Control,' requires verification that the Suppression Pool level is greater than 5.25 feet prior to opening all ADS valves. Explain why this limit on Suppression Pool level is imposed for Emergency l RPV Depressuri:ation. (1.0) i i (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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@@919b931$@h_$$$$$$k QUESTION 7.10 (2.00) a. S01-R43, " Division I and II Diesel Generator System,' cautions against shutting down both engines at the same time if the Division I and Division II Diesel Generators are running simultaneously. Explain why shutting down both engines at the same time would be undesirable. (1.0) b. Explain why S01-R43 cautions against reducing diesel generator load below 100 MW when synchronized with the grid. (1.0) l QUESTION 7.11 (3.50) I' A transient has occurred with a resulting reactor ecram. However, several rods remain stuck out beyond position 02. At the ""' 45%$, all Reactor Pressure Vessel (RPV) water level indication is lost and'thus Attachment 4, 'RPV Flooding,' Steps 5 through 7 of PEI-B13, ' Reactor Pressure Vessel Control,' is ultimately entered. (PEI-B13, Attachment 4, Steps 5 through 7 are attached for reference.) ExP ain why, in Step 5, all the injection into the RPV is terminated l a. or prevented except that from the Standby Liquid Control and Control Rod Drive Hydraulic Systems. (1.0) j b. Explain why, during injection in Step 7, RPV pressure must be kept above the Minimum Alternate RPV Flooding Pressure (MARFP) but as low as practicable. (1.0) c. Explain what a decreasing RPV pressure w o u l-o indicate during q injection in Step 7. (Assume the number of open SRV's remains j constant.) (0.5) l d. Explain why, in Step 7, the preferred systems for injection are the Motor Driven Feedwater Pump, the Reactor Feedwater Booster Pumps, i and the Control Rod Drive Hydraulic System. (TWO reasons requir d.) l (1.0) I l t l 1 l l 1 I l (***** END OF CATEGORY 07

• • • • • )

1 ~ l'

gg 5 h'ovs OM4C: PEI-B13 Page: 69 Rev.: 1 Atrechment 4 (Cont.) IF WHILE EXECUTING 1 to 7 A. RPV level can be detarmined, I w an .. new ehan 1. If all control rods are i eso Inserted to or beyond aco position 02, 8 no then exit this attachment and proceed to execute concurrently: e so - EPV Control at step 3.2.5 (page 26). or(,,. - - RPV Contrel ae srep '!Z' i*' ";' *" '*;;; 't'" %'"* ,n,.,,, .o.,.... 3.3.2 (page 38). " * ' ' " ' " " " * ~ ' '"" 2. E any control rod is not inserted to g I beyond position 02, then exic this attachment and proceed to execute concurrently: 1 - RPV Control at step 3.2.5 (page 26). b Atcachment 5. Power

• Control Using RPV Level.

~ p wh r g - - - - - - ' - - - - - - ' ' ' - ' - - - - - - - - ~ ~ - - ~ ~ " - - - - -

g i t OM4C: PEI-B13 Page: 70 Rev.: 1 (Cont.) e RPV Flooding 5. Perform the following actions to terminate' and prevent inj ec tion I into the RPV except from SLC and CRD until RPV pressure is below f the Minimum Alternate RPV Flooding Pressure, Figure 4. i _ CAUTION A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage. To prevent opening of the LPCS and LPCI injection valves while performing the following steps, two operators may be required. If, any of the systems listed below are not operattng, then perform a. the applicable injection prevention section. System Section EPCS Injection Prevention LPCS & LPCI A Injection Prevention 5.13 5.14 LPCI B & C Injection Prevention 5.15 b. If any of the systems listed below are operating, then manually o7erride the injection valves to the CLOSE position. -EPCS -LPCS -LPCI A -LPCI B -LPCI C NOTE: y an automatic RCIC Initiation signal, RPV level 2 or manual initiation, is received, then RFPs and the main turbine will trip. Terminate injection from the feedwater system and RCIC. c. 4 m

.) OM4C: PEI-B13 Pages. 71 Rev.: 1 (Cont.) 1 -IF WHILE EXECUTING i 1 to 7 l A. RPV level can be determined. ' l then ""*"'o**' I 1. Il all control rods are inserted to el eyond b position 02, a 2.o -then 4 'so exit this attachment s 'So and proceed to execute e '80 concurrently: 7 e oo - RPV Control at step 3.2.1 (page 26). - RFV Control ae eeep U." O.'"*a. T 7.AE*7.*U. U.7.*** 3.3.2 (page 38). a7?'#.M%.E*.'?4",*El*.UA""* ' ' * * * ' ~ " " ' * * * * * * * * * ' ' " "

• 2.

E any eontral rod is not inserted to or beyond position 02'. then exit this attachment and proceed to execute concurrently: ' - RPV Control at step 3.2.1 (page 26). - Attachment 5, Power Control Using RPV Level. U 9 O M -aMM .n.~

f l OH4C: PEI-B13 i Page: 72 Rev.: l' , (Cont.) RPV Flooding Procedure Steps Contingency Steps 5. (Cont.) d. If 3 or more SRVs are d. None 1 opened, then close the following valves to prevent possible_ damage to the main steam lines: 1 MSIVs 1B21-F016 MSL DRN & MSIV BYP INBD ISOL f IB21-F019, MSL.DRN & MSIV BYP OTBD ISOL 1E51-F063, RER 6 RCIC ST SITPP INBD ISOL 1E31-F064 RER & RCIC ST SUPP OTBD ISOL 1E51-F076. RHR & RCIC ST .SUPP WARM UP ISOL 6. Commence aligning at least two of the followin's injection systems in i 4 the priority listed with the injection valves closed. j I System . Alignment j l MFP.or RFBP Section 5.3 HPCS and MFP L8 Trip Bypass ] i RHR A RHR A TEST VALVE TO SUPR POOL, IE12-F024A, closed. RHR B RER B TEST VALVE TO SUPR POOL, IE12-F024B, closed. ) LPCS Test Return-Mode HPCS Test Return Mode RER C Test' Return Mode 7. When RPV pressure has decreased 7. I,f,n_o,SRV can be opened, then f o to less than the Minimum Alternate proceed. RPV Flooding Pressure. Figure 4, ) then perform the following actions to control RPV inj ection. 1 .. l

OM4C: PEI-513 Paga: - 73~ Rev.: ' 1 l l Attachtint 4 (Cont.) IF WHILE EXECUTING j i i 1 1 to 7 l l A. RPV level can be determined. m rv \\ a=.m.s.a. a.w than wv. o 1. JJ, all control rods are i j inserted to g beyond position 02, then j iso exit this attachment iso and proceed'to execute e concurrently: r 'io so e - RPV Control at step j J 3.2.5 (page 26).. ort 1 r....,, .. u, ........v.m.. m 3.3.2 (page 38). 377'.!Mo**4.8.7,*.*S*4','.0**.E"#.S'" ' J ..... -.., i a.........

3. n e s..

- RPV Contto1 at seep ' ' ' " ' ' ' " ~ " ' ' " * ' ' ' ' ' " " " * * * * ' ' " ' ' 2. I_f,any control rod is not inserted to or beyond position 02 then exit this attachment and proceed to execute c concurrently : - RPV Control at step 1.2.5 (page 26). - Attachment 5. Power Control Using RPV Level. e vg __a_.__ _ _ _ _ _ __ _ _ _

-u i-OM4C: PEI-B13 Page: 74 Rev.: 1 (Cont.) R RPV Flooding CAUTION A rapid increase in injection into the -RPV may induce a large power excursion and result in substantial core damage. If injecting inside the. shroud, then increase injection very slowly. 4 4 Commence and slowly increase injection into the RPV with' the following 'd a.' systems until: one oj; more SRVs is open, and RPV pressure is above the Minimum Alternate RPV Flooding Ptassure (MARTP). Control injection to maintain'one of more SRVs open and RPV pressure above the MARFP, Figure 4, but as low as practicable. j I System Special Instructions i MFP Section 5.3 HPCS and MFP L8 Trip Bypass j RFBP ] CRD j l If nct SRVs are open, or RPV pressure cannot be increased above the MARFP, Figure 4, then comnence and slowly increase injection into the RPV with the systems or subsystems in the priority listed as .I necessary to establish at least one SRV open and RPV pressure above the MARFP. Control injection to maintain one of nore SRVs open and ,RPV prassure above the MARFP, Figure 4, but as low as practicable. System Bypass Section RHR A RER ISOL BYPASS E12-F053A on P629 5.16 RHR B RER ISOL BYPASS E12-F053B on P618 5.17 LPCS LPCS LOGIC BYPASS E21-F012 on P629 5.18 j EPCS HPCS & MTP L8 Trip Bypass 5.3. EFCS Injection Valve Seal In Logic Defeat 5.4 HPCS LOGIC BYPASS E22-F023 on P625 5.19' RHR C LPCI C Injection Valve Seal in Logic Defeat 5.5 LPCI C LOGIC BYP E12-F021 on P618 5.20 Alternate Injection Subsystems -RHR Loop B Containment Flood Mode 5.7 -Condensate Alternat'e Inje'ction 5.8 -Condensate Transfer Alternate Injection 5.9 -SPCU Alternate Injection 5.10 '-SLC Alternate Injection of Domin Water 5.11 -Feedwater Leakage Control System 5.12 b. When all control rods are inserted to cg; beyond position 02, then proceed to step 2 (page 60). e mi ~

---

_-------_a

umacoccacuococcoaccomacacccaoamoaaaaaaaaaaaaoa-oaamemaccaa 1 QUESTION 8.01 (2.50) The plant has been operating at 80% power for 3 months. A security guard reports that access to the Division I Remote Shutdown Panel has been completely blocked by a scaffold. Using the attached portions of Technical Specifications: a. Is the remote shutdown panel considered operable? Why or Why Not? (1.0) b. Upon returning to the Shift Supervisor's office, you overhear the Instrument Maintenance Foreman discussing the results of the Division 2 Remote Shutdown Panel monthly chann'1 checks. Three of the 14 instruments failed to respond during the channel checks. Paperwork is being initiated for calibrations. As the Shift Supervisors what action (s), if any, are you required to initiate to comply with Technical Specifications? (1.0) c. You subsequently receive a call from the Maintenance Foreman that installed the scaffold blocking the Division I panel. The scaffold has been installed for two weeks by an approved Work Order. They have about 3 shifts of work left to complete the job. How does this information change your required action to comply with Technical Specifications? (0.5) OUESTION 8.02 (3.00) Due to heavy snowfall and minimum manning during the Christmas holiday season, the onshift crews have been using overtime up to the limits of the Svidelines. The plant is operating at 1050 Mwe on Saturday, December 19th. a. Three members of the oncoming afternoon shift call in and report that they are snowed in at home. The dayshift crew members will exceed the overtime guidelines if required to be held over. How can the additional overtime be approved? (1.0) b. Due to a planned trip to the home of relatives, the offgoing STA makes arrangements for a replacement to be ansite within two hours after he leaves. Is this acceptable? (0.5) Why or Why Not? (0.5) c. The State Police subsequently close the roads from 10'00 p.m. until 7:00 a.m.. Since relief is not possible, the Unit Supervisor and Shift Supervisor decide to take turns taking 2-hour naps in the STA's office. Explain how this could be legally justified to the NRC using the criteria of PAP 0110, ' Shift Staffing.' (FOUR items required.) 1 (***** CATEGORY 08 CON'INUED ON NEXT PAGE

• • • • • )

um6 w d d*m4=m' = w a ~

l QUESTION 8.03 (1.50) Du. o a manufacturing defect, the Reactor Water Cleanup (RWCU) System non-regenerative heat exchanger has developed a tube leak. The Nuclear Closed Cooling Water System is slowly becoming contaminated. a. Procedure PAP-0201, ' Conduct of Operations' requires a condition report to be written. Why? (0.5) b. For system operation to continue, one of two conditions must be met. Identify the TWO conditions outlined in PAP-0201 ' Conduct of Operations. (1.0) i QUESTION 8.04 (1.50) l Following shift turnover, the Unit 1 Supervisor delivers the quarterly Division 3 HPCS pump flow test surveillance for final review. Due to a question on required pump flow, the Unit Supervisor obtained the previous three surveillance. The current surveillance was completed on May 30, 1987. You notice that the previous surveillance were completed February 15, 1987, November 10, 1986, and August 10, 1986. Is this acceptable? Show your work. Use the following days per monthi August 31; September 30; October 31; November 30; December 31; January 31; February 28; March 31; April 30; and May 31. i r f 1 I l (***** CATEGORY 00 CONTINIJED ON NEXT PAGE

• • • • • )

~

QUESTION 8.05 (2.00) 'Near the end of an extended outage, all ECCS systems are being lined up for standby status. The person performing second verifications on the LPCS System calls to report that the position indicator is missing on the manual instrument root valve (E21-F506) that isolates the ADS permissive switches. The valve is required to be open. a. How can the person verify that the valve is open to comply with PAP 0205, ' Operability of Plant Systems?' (0.5) b. The System Engineer, when contacted about the missing position indicator, explains that the original cast indicator parts on these i and the motor operated valves, are prone to breakage. He had Mechanical Maintenance machine a bunch of replacements in the shop. l He thinks they can modify one to fit and initiates a work request to replace the position indicator. He explains that this is an easy job ] since it doesn't even require a Work Order number. They have done I several of these already because system integrity, operability, and 1 reliability are not affected. Provide three reasons why this is unacceptable? (1.5) QUESTION 8.06 ( 2.b On November 3, 1986, to support equipment and personnel access during Control Rod Drive maintenance, the Maintenance and Security personnel blocked opei. Door Ax-412 to the secondary containment annulus area for approximately 90 minutes. The security guard monitored access through the door to comply with security requirements. The plant was in cold shutdown. a. This creates a problem in Technical Specifications. What is it? (1.0) b. What indication (s) is/are provided in the control room to make operator (s) aware of a problem? (0.5) c. When notified of this situation, what immediate acttion(s) would be required by Technical Specifications? (0.5) r.k h oeed w e-FAF 0 2 2O r

• S emity Jtan c n r a c Ar ing4 fee-1-ifr3-end M n i n tena tree-Oct agewL h e s baan revised to_. help prevent rep +t+t-iert-o f-a g lair pu tho esr o c e d o r o un changed.

( 0. () th i s p r ob l e nt.... Br.iefly_htN D (***** CATEGORY 08 CONTINUED ON NEXT PAGE

• • • • • )

.,m. 4 6@ e

i . 1 0' l lGUESTIO'N? 8.07 (1 50) As. Shift' Supervisor,1you receive a cal 1 from the Radwaste Technician.. l -They-are ready to. initiate a liquid radwaste discharge to the Emergency - l Service Water-Discharge. :You notice from: shift turnover that the l discharge' radiation monitor.is inoperable. Identify the two Technical Specification 1 conditions'that must be satisfied for the: release to

proceed.

(1 5) R l L i u OUESTION~ 8.08 (2.00) i l L, On March 2, 1987,~a,reacto'r scram occurred.on loss of feedwater with I subsequent level 2 ECCS initiation and' level recovery.. -l a. The. event required a red phone call to the NRC as required by 10 CFR 50.72. Identify two reasons why the call was. required. l 10 CFR 50.72 attached. (1.0) -b. 10 CFR 50.73 also required a Licensee Event Report to.be prepared and submitted. Why?.10 CFR 50.73 attached.~(0.5)

c..

Technical Specifications requireLa special report to.be submitted to the NRC for.this event. Why? (0.5) ' QUESTION '8.09 (1.00)' The1 plant is operating at 80% rated thermal power. Channel functional tests are performed on the Main. Steam Line Radiation Monitors. Channels'A and D test UNSATi Channels B and C are SAT. Maintenance has no estimate 1 of repair time and will not be able to commence troubleshooting and repair-q for/st least 16-20 hours. Which.one.of'the following actions'most correctly complies with the requirements imposed by Technical Specifications? Applicable Technical Specifications are attached. a. De'in at least hot shutdown within 12. hours. b.- Close the affected isolation valves.within one hour and declare the monitors inoperable. c. Place either RpS Trip System A or B in the tripped condition within i hour and be in at least hot shutdown within 12 hours and in cold shutdown within the.next 24 hours. d.' Be in at least startup within 6 hours. (***** CATEGORY 08 CONTINUED'ON NEXT PAGE *****) m m.m.

QUESTION 8 10 (2.00) 1 1 The plant is operating at 90% of rated power on the midnight shift Sunday norning. The Shift Supervisor complains of severe chest pain. Provisions are'made for him to be taken to'the hospital. )( a.- What two individuals, in order of succesfion, assume the responsibilities of the Shift Supervisor per PAP 0110, " Shift Staffing?' (1.0) b. What two additional actions must be initiated? (1.0) l -GUESTION 8.11 (3.00) Indicate whether the following statements are TRUE or FALSE: a. STA's are required to be Licensed Senior Operators, b. A Shift Supervisor may concurrently fill the position of the STA while on shift. c. An Operator License is required for a person to perform a core alteration. d. All core alterations must be directly supervised by a Licensed Senior Operator or Senior Operator Limited to Fuel Handling. e. Fire Brigade composition may be less than the minimum requirements for a period of up to 2 hours including shift changes. I f. Fire Brigade members may be diverted to other emergencies during a j fire if deemed appropriate by the Shift Supervisor. j l l I (***** CATEGORY 08 CONTINUED ON NEXT PAGE

• • • • • )

b6

• =

= re w a

j - . l t i ) gr< QUESTION B.12 (1.50) I at Regarding ' Temporary Changes to Iristructions,' PAP 0522, state whether the following items are TRUE or FALSE' .c a. An Instruction Temporary Change is a change made to an appr'ved a instruction prior to the next revision. (0.5) be A Non-Intent Temporary Change may require a 10 CFR 50.59 applicabil'ity check. (0.5) co Intent. temporary changes are conditionally approved by two members of the plant staff management knowledgeable in the affected apear at f, least one of whom is either the Shift Supervisor or Unit Supervisor. (0.5) _ i f i QUIdTION 8.13 (1.50) During plant startup, the plant is ready to proceed from Mode 4 to Mode 3. IOI-1, ' Cold Start-Up,' Prerequisite No. 13 requires that primary and sycondary containment integrity be established, in part, by completing to pap 1114, ' Operational Condition Change Checklist" which describes various Type A, B, and C Containment Leakage Tests. Describe the difference between Type A, B', and C leak rate tests or give an enample of each. (1.5) l N 1 \\ l t J } i / (***** END OF CATEGORY 08

• • • • • )

(************* END OF EXAMINATION

• • • • • • • • • • • • • • • )

m -6 m .,g en /_ -

l 'i i 4 a, e m c.m.issi.sc on q 4 tion th the IW activity, as may be

any other method which Will ensure j

.q y the conditions of the llo-c.f that a report is made sa socra as practi-l L1 permit by the rules, regulauo and ca! to the NRC Operations Center.' .g orders the Commtanton in eff ung '(11) The licensee shall notl*y the 8

• ^'
  • " " L NRC im'nediately after notification of tthe gg.) Witb.

to any prod LNu. the appropriate State or local agencies j ni 1 ar. timesax is of a type bed' to and not later timn one hour after the ] 8L Ileit(b) er i 23 of this or a testing thne the lleensee declares one of the il. factutyJ each e and h holder of C Emergency Classas. j i a construcuan pe it a upon each tasu-(4) When mak1ng a report under e. anee of its annual. c report lecluding the certified statements, file a paragraph (aM3) of this section, the 11- %py thereof with Director of Nuclear censee aha!! identify;

c. actor Regulatto

8. Nuclear Eegula.

(t) The Emergency Chas declared: or t v ConuWasion, ash ston. D.C. 23666. (11) Either paragraph (bX1), "One-l 'T ' Hour Report." or paragraph ibX2).- I

e "Four. Hour Report." as the paragraph r

A i of this section requidng notification of l (*)*** the Non-Emergency Event, uha t[su i t on a lacem (b) Non emerpency events--(1) One-3f 'page and shall be===9ied by a hour reports. If not reported as a dec-I IIst w idemtifies the current pires of the laration of an Emergency Class under 1 'I following pase replacem

t. One paragraph (a) of this section, the 11 3*

ortsmal and 12 additional les of censee shall notify the NRC as soon as F requhtd information shall be fil with practical and in all cases within one a e Diretter of Nuclear Reactor Regul ton, hour

• the occurrence of any of the t-tifs. Ni,,r4ar Regulatory Commtssion. gogin.

.g. 1 i i Washingtoct, D.C. 20668. is. The initiation tsf any nucle $r shutdown required by the a ~

's Techckal Specifications.

' 5 50.72 Im.nediate notification veguire. ..f) Any deviation ftem the plant's .uchnical Specifications authorises ments for operating nuclear power,re. '#I "

• pursuant to i 50.54(x) of this part.

'I' (11) Any event or condition during Y-(s> General reeufrements.8 (1) Each I . nuclear power reactor licensee licensed ' opention that results in the condition a i of the nuclear powerplant. Including e

under iE21tb) or i 50.22 of this part fta principal safety barriers, being seri-shsM cotify the. NRC Operations ously degraded; or results in the nucle-la Center via the Emergency Notification

/ nr power plant being: 8 System of: (Afin an unanalyzed condition that 1 (1) The declaration of any of th*J i significantly ' compromises plann{ t e Emergency Ut.ases specified in the 11* l safety; e, censee's approved Emergency Plan;8 (B) In a condition that is outside the. l e or design basis of the plar.t; or (11) Of those non Emergency events j .1 specified in paragraph (b) of this sec* (C)In a cewlition not covered by the plant's operatirvf and emergency pro-y !!cn. cedures. ,R (2) If the !dntraen!k Notification ( 111 ) Any natural phenomenon or Bystem 19 lirioperative, the licensee 3, shall makel,the twuired notifications other external condition that poses an actual threat to the safety of the r.u-s. via commerchst - telephone service, le other dedicated telephone system, or cler.r power plant or significantly ham-

l pers site personnel in the performance f* '

s of duties necessary for the safe oper-s 'Other requirements fr.t 'mraediate notift. 4 tion of the plant. i s-cation of the NRC by Joensed operating nu. (iv) Any event that results or should clear power reactm are comained else-have resulted in Emergency Core . where in this Casster, in particular, j b 16 20.208,20.403,60.38, ant 73.7L i 3 'These Emergency CIrmes are acktressed 8 Commercial telephone number of the la Appendix Eof this past. NRC Operations Center is (202) 951-o550. 7 n 509 i e - JO,7' ^

I 1 1 I f 50J2 10 CPR Ch. I (1-1-47 Edition) D l Cooling System (ECCS) discharge into when averaged over a time period of 1-1 -1 the reactor coolant system as a result one hour, a of a valid signal. (v) Any event that results in a major (B) Any liquid effluent release that loss of emergency emessment capabil-exceeds 2 times the limiting combined ity, offsite response capability, or com-Maximum Perminalble Concentration i (MPC) (see Note 1 of Appendix B to munications capability (e.g., signifi-o 1 cant portion of control room indica-Part 20 of this chapter) at the point of p l tion. Emergency Notification System, entry into the receiving water (i.e., un-L or offsite notification system). restricted area) for all radionuclides e', (vi) Any event that poses an actual except tritium and dissolved noble 4 P t threat to the safety of the nuclear gases, when averaged over a time d. I power plant or significantly hampers period of one hour. (Immediate notifi-w. site personnel in the performance of cations made under this paragraph ca. l duties necessary for the safe operation also satisfy the requirements of para. ol ' of the nuclear power plant including graphs (a)(2) and (bX2) of I 20.403 of rt fires, toxic gr* releases, or radioactive Part 20 of this chapter.) st releases-(v) Any event requiring the trans. ID - l l (2) Fosr hour reports. If not repurt-port of a radioactively contaminated ed under paragraphs (a) rr (bMI) of person to an offsite medical fac"ity this section, the licensee shall notify for tres,tment pl the NRC as soon as practical and in all (vD Any event or situation, related pl cases, within four hours of the occur' to t.he health and safety of the pubile or onsite personnel, or protection of hi ) ( y ent, o wh le the reac-the environment, for which a news re-fit 1 tor la shut down, that, had it been lease is planned or notification to found while the reactor was in oper, other government agencies has been Ti i ation, would have resulted in the nu. or w!U be made. Such an event may in-pt ; clear power plant, including its princi-clude an onalte fatality or inadvertent l l pal safety barriers, being seriously de-release of radioactively contaminated tu graded or being in an unanalyzed con-materials. pt dition that significantly compromises (c) follotoup nottrication. With re-sa plant safety, spect to the telephone notifications ed (iD Any event or condition that re-made tmder paragraphs (s ? nnd (b) of PC sults in manual or automatic sctuation this section, in addition to making the of any Engineered Safety Feature required initial notification, each 11-sii i (ESP), including the Reactor Protec, censee, shall during the course of the sa tion System (RPS). However, actu-event: ation of an ESP, including the RPS, (1) Immediately reporf (D any fur-th e that resulta from and is part of the ther degradation in the level of safety preplanned sequence during testing or of the plant or other worsening plant . pl: a reactor operation need not be report; conditions, including those that re-ed. ce quire the declaration of any of the ( 111 ) Any event or condition that Emergency Classes, if such a declara-alcae could have prevented the fulfin. tion has not been previously made, or ot ment of the safety function of strue. (iD any change from cr,e Emergency ac tures or systems that are needed to: Class to another, or (110 a termination ch (A) Shut down the reactor and main. of the Emergency Class. pe ; tain it in a safe shutdown condition. (2) Immediately report (1) the r esults an 4 (B) Remove residual heat, of ensuing evaluations or asseannents op (C) Control the release of radioac-of plant conditions (11) the effective-( tive ms.terial, or su' ness of response or protective meas-(D) Mitigate the consequences of an ures taken, and (iii)Information relat-ati accident. tu: ed to plant behavior that is not under. (ivXA) Any airborne radioactive re-stood. tec lease that exceeds 2 times the applica-(3) Maintain an open, continuo"s thi i att ble concentrations of the limits speel-

• led in Appendix B. Table II of Part 20 communication channel with the NRC pn l Operations Center upon request by of this chapter in unrestricted areas, the NRC.

res ' ed. 510 M 72 l 1 l l

l 1 h ~ '10 . sn. : 0.i.s7 adelen) Nuclear Reevletery Commission $ 50 73 4 rag Cver a time period of 148 FR 30o48. Aug. 29,1983; 48 FR 40882. (v) Any event or condition that t. sept.12.1983) ~ alone could have prevented the fulfill-sy liqu sffluent release tha ment of the safety function of struc- '2 times the limiting combin 5 60.73 Licensee event report system. tures or systems that are needed to: m Pe ble Concentration (a) Reportable events. (1) The holder (A) Shut down the reactor and main. see No 1 of Appendix B of an operating license for a nuclear tain it in a safe shutdown condition; af this c pter) at the point f power plant (licenue) shall submit a (B) Remove residual heat; to the iving water (i.e., Licensee Event Report (IER) for any (C) Control the release of radioac-d area), f r all radlonucli event of the type described in this tive material; or tritium d dissolved a le paragraph within 30 days after the (D) Mitigate the consequences of an then ave ed over a e discovery of the event. Unless other-accident, f one hour. Immediate n ifi-wise specified in this section, the 11-(vi) Events covered in paragraph made unde this p Th censee shall report an etunt regardless (aX2XV) of this section may include sfy the rea ments of ara-of the plant mode or power level, and one or mere procedural errors, equip-aX2) suid (b 2) of $ 20. 3 of regardless of the significance of the ment failures, and/or discovery of if this chapte ) structure, system, or component that design, analysis, fabrication. construc-y event requ .g the rans. initiated the event. tion, and/or procedural inadequacies. a radioactive con ted (2) The licensee shall report: However, individual component fall- 'i o an offsite edlcal scility (iXA) The completion of any nuclear ures need not be reported pursuant to 'ntnt. plant shutdown required by the this paragraph if redundant equip-ty event or sit tion. related plant's Technical Specifications; or ment in the same system was operable ralth and safety ft public (B) Any operation or condition pro-and available to perform the required 2 personnel, or to lon of hibited by the plant's Technical Spect-safety function. 'onment, for whi news re. fications; or (vil) Any event where a single cause planned or not fl tion to (C) Any deviation from the plant's or condition caused at lean one inde-vernmtnt agenci as been Technical Specifications authorized pendent train or chknnel to become in-t made. Such an ev t may la. pursuant to i 50.54f.z) of this part. opersble in multiple systems or two in-onsite fr.tality or advertent (11) Any event or condition that re. dependent trains or channels to radioactively co ted sulted in the condition of the nuclear become inoperable in a single system power plant. including its principal designed to: fotoup notificati. Ith re-safety barrie ts, being seriously degrad-(A) Shut down the reactor and main-the telephone tott testions ed, or that resulted in the nuclear tain it in a safe shutdown condition; $er paragraphs ( ?e (b) of power plant being: (B) Pemove residual heat; on, in addition m ng(ne (A)In an unanalyzed condition that (C) Control the release of radioac-initial notific lon,' h 11-significantly cornpromised plant tive material; or

• all during the course fthe safety; (D) Mitigate the consequences of an (B) in a condition that was outside accident.

nediately (1) an fur-the design basis of the plant; or (v111)(A) Any airborne radioactivity adition in th level of ety (C)In a condition not covered by the release that exceedeC,2 times the ap-Ant or other orsening ant plant's operating and emergency pro-p11 cable concentrations of the limita i

s. Including those that re-ceduras.

'specified in Appendix B. Table II of

declaratto of any of he-( 111 ) Any natural phenomenon or Part 20 of this chapter in unrestricted

y Classes, such a deel

} other external'.ad' tion that posed an areas, when averaged over a time , tot been pr viously made,.. 1 r actual threat to the safety of the nu. period of one hour.

hange fro one Emergen clear power plant or significantly ham-(B) Any liquid effluent release that

.nother, or 111) a terminatio tergency C pered alte personnel in the perform-exceeded 2 times the limiting com. l ance of duties necessary for the safe bined Maximum Permissible Concen. .ediately port (1) the resul operation of the nuclear power plant. tration (14PC)(see Note 1 of Appendix i g evalust ns or assessments (iv) Any event or condition that re. B to Part 20 of this chapter) at the mnditic. G1) the effect:n-suited tn manual or automatic actu-point of entry into the receiving water j esponse r protective mens-ation of any Engineered Safety Fea-(i.e.. unrestricted area) for all radionu-l 1, and ( )information relat-ture (ESF), including the Reactor Pro-clides except tritium and dissolved .t beha or that is not under-tection System (RPS). However, actu. noble gases, when averaged over a ation ci an ESF, including the RPS, time period of one hour, ntain open continuous that resulted from and was part of the (ix) Reports submitted to the Com. 'ation hannel with the NRC preplanned sequence during testing or mission in accordance with paragraph a Ce ter upon request by reactor operation need not be report- (aX2)(v111) of this section also meet the ed. effluent release reporting require- __] 511 36,73 O

1^ I50.73 10 CFR Ch. I (1 187 Edition) 94888 ments of paragraph 20.405(a)(5) of will be published in the FxDERA2. Rac. vevent. 'l Part 20 0f this chapter. Isrza. Copies may be obtained from lthe ava ' (x) Any event that posed an actual the Institute of Electrical and Elec. icornpone threat to the safety of the nuclear tronics Engineers, 345 East 47th iformed power plant or significantly hampered Street. New York NY 10017. TM Std ' ponents site personnel in the performance of 803-1983 is available for inspection at' during i duties necessary for the safe operation the NRC's Technical Library, which is. (4) ^ of the nucle:.r power plant including located in the Phillips Building. 7920 i actions fires, toxic gas releases, or radioactive Norfolk Avenue, Bethesda, Maryland;

• event.- 1 releases.

and at the Office of the Federal Regis. probabi ter,1100 L Street, NW, Washington, ;; in the f (b) Contents. The Licensee Event Report shall contain: DC. (5)R' (1) A brief abstract describing the (0) For failures of components with, events - major occurrences during the event, multiple functions. Include a list of jknown including all component or system fail-systems or secondary functions that (6) T 1 ures that contributed to the event and were slao affected. ' of a pt i significant corrective action taken or (H) For failure that rendered a train nizatto ' planned to prevent recurrence. of a safety system inoperable, an esti. the eV (2)(D A clear, specific, narrative de-mate of the elapsed thne from the dis-inforn) scription of what occurred so that covery of the failure until the train the pl8 knowledgeable readers conversant was returned to service. (c) ! < with the design of commercial nuclear (I) The method of discovery of each .Comrej power plants, but not familiar with component or system fa!!ure or proce, to sut ; the details of a particular plant, can dural error. tion I t understand the complete event. (JXf) Operator actions that affecteo graph (11) The narrative description must the course of the event, including op. missic include the following specific informa-erator errors, procedural deficiencies, rial b tion as appropriate for the particular or both, that contributed to the event. stand event: 1 -(2) For each personnel error, the 11 signif 1 (A) Plant operating conditions censee shall discuss: suppl l before the event. (t) Whether the error was a cogni-made i (B) Status of structures, compo-tive error (e.g., failure to recognize the subre 1 nents, or systems that were inoperable actual plant condition, failure to real. quesi] at the start of the event and that con-Ize which systems should be function. to th " tributed to the event, ing, failure to recognize the true (d) l (C) Dates and approximate times of nature of the event) or a procedural Ever occurrences. error; Fort, (D) The cause of each component or (ii) Whether the error was contrary 30 t l system failure or personnel error,' if 'to an approved procedure, was a direct ever{ known. result of an error in an approved pro-Reg i (E) The failure mode, mechanism. cedure, or was associated with an ac-in ! ! and effect of each failed component,if known. tivity or task that was not covered by (e i an approved procedure; cop' (F) The Energy Industry Identifica-(iii) Any unusual characteristics of sub tion System component function iden-the work location (e.g., heat, noise) pro tifier and system name of each compo-that directly contributed to the error; suf: i nent or system referred to in the LER. and pro ; I (f) The Energy Industry Identifica. (iv) The type of personnel involved ing i tion System is defined in: IEEE Std (i.e., contractor personnel, utility 11-(: 803-1983 (May 16,1983) Recommend-censed operator, utility nonlicensed qui 1 ed Practices for Unique Identification operator, other utility personnel). qus l Plants and Related Facilities--Princi-(K) Automatically and manually ini-of ples and Definitions. tlated safety system responses, j DL ' (2) IEEE Std 803-1983 has been ap-(L) The manufacturer and model leti proved for incorporation by reference number (or other tuentification) of t tic i by the Director of the Federal Regis-each component that failed during the ur ! l

ter, event.

A notice of any changes made to the (3) An assessment of the safety con-et l material incorporated by reference sequenoes and implications of the re l 512 t 16.73 i

l f 50.78 N"8I E Nucleme Regatetery Commission ) censees to report " Reportable Occur-f event. This assessment must include rences" as defined in individual plant A-Copies may ob di en the availability of other systems or j that could have per-Technical Specifications.- stitute i Electrical d ec. f componentsformed the same function as the com-148 FR 33858. July 26,1983, as am 'En ers. 345 East 7th New Yo L NY Std ponenta and systems that failed

• • tl 4

13 is av abl n at during the event. 86 .C's Tec ic .w chis '(4) A description of any corrective Ernerin Dars Nort At 61 FR 40310. in the IUlps B ding 7920 ; actions planned as a result of the Nov. 6,1986. I 50.73 was amended by revis- . Avenue Bethesd ' the Offics f th* land; t event including those to reduce the ing parasraphs (c) and (d), effective Janu- 'P"3

gis, probability of similar events occurring ary S.1987. For the comenience of the user,

)0 L Str

• W"8 (5) Reference to any previous similar. the superseded text la set forth below.

- in the future. n. or failures f e functio i cfude ' 18 with events at the same plant that are e 50.73 Licensee e+ent report system. list of , known to the licensee. or secon y funct! na that (6) The name and telephone number so affected,

of a pers n within the licensee's orga-(e) supplemental informetton. The com-Mr f.*Uure th rende d a train nirAtton who is knowledgeable about mission may reautre the licensee to submit l

' ety system perabl, an esti-the event and can provide additional spec 1De additional information beyond that f.he el206ed e fr the dis-information concerning the event and required by paragraph (b) of this section if of the failur th' train the plant's characteristics. the Commission finds that supplemental trned to servic ' (c) Supplemental information. The material ic necessary for complete under-e method of d feach Commission may require the licensee standins of an unusuaMy complex or signin. ent or syste e or proce, to submit specific additional informa-fb ade in ENg aYn t ror. tion beyond that required by para. info on Operr. tor actio at affected graph (b) of this section if the Com-licensee shall submit the requested informa-se of the event clu D-mission finds that supplemental mate

• tion as a supplement to the initial LER.

rrors. procedu defiel n a is necessary for complete under-(d) Submission of reports Lleensee Event that contribute to th' 8 Vent.

standing of an unusually complex or Reports snust be prepared on Form NRC r each personne tror. the 11 sign!!! cant event. These requests for 366 and submitted within 30 days of discov-1all discuss: supplernental information will be ery of a reportable event or situation to the a a cognl-made in writing and the licensee shall U.S. Nuclear Regulatory Commission. Docu-1 ether the e ment control Desk. Washington, D.C. r (e.g. faDure r gaf=e the submit as specifled in i 50.4, the re-20555. The Meensee shall also submit an ad. lant condition. fah to real-quested information as a supplement ditional copy to the appropriate NRC Re.

** systems sho d unction-to the initial LER.

gional Office usted in Appendix A to Part

ure. to rec

1. the true (d) Submission of reports. Licensee 13 of this chapter.

'f the event) M A ocedural Event Reports must be prepared on + Form NRC 366 and submitted within lether the e rw ntrary 30 days of discovery of a reportable ') roved pr ure, w direct event or situation to the U.S. Nuclear US SArEGUARDs Ac an error an p ed pro-t Regulatory Commisalon, as specified it was ass la "" Ac* in 5 50.4. 8 50.78 In 11ation information veri- .. task th:t. t cov red by (e) Report legibility. The reports and fication. ved proc copies that licensees are required to i:ly unusu characteris ics of submit to the Commission undet the Each holder s const ion permit --.g e) provisions of this section must be of shall,if reques by t Commission. locatic, g,g etly cont $buted, 5th'e FMf; sufficient quality to permit legible re" submit installati ormation on p ti d miemgraphic pmcess' Form N-71, permit ication thereof e type f personnel inv ved 18 8-by the Internati tomic Energy tractM personnel, ut!D 13 () Exemptions. Upon written re-Agency,andt such ter action as I Perr.to ut!Dty nonlice d quest imm a licensee iricludMg ade-may be nece ry to ina ement the l Other tility personnel)- quate justification or at the initiation gu Agr ent, g omatJ y and of the NRC staff, the NRC Executive 8[ ,,'g gg sty sy tem responses 75.11 t ush 75.14 of this chap r.

• "" "*I' em ufacturer and moc 1

r tions to the reportin'g requirements (49 9627, May 9.19841 i or her identification) i Jon; t that failed dudng th )' under this section. l (g) Reportam ocmrmes. N & quirements contained in this section l ase mint of the safet d imputations ofthe replace all existing requirements for 11-513 56,73 i i { i

R

• DEFINITIONS OPERABLE - OPERABILITY 1.29 A system, subsystem, train, component or' device shall be OPERABLE or have g

OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). OPERATIONAL CONnITION - CONDITION 1.30 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2. PHYSICS TESTS 1.31 PHYSICS TESTS shall be those tests performed to measure the fundament nuclear characteristics of the reactor core and related instrumen described in Chapter 14 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59 or 3) otherwise approved by the Commission. PRESSURE BOUNDARY LEAKAGE 1.32 PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-is 'g ) a reactor coolant system co'mponent body, pipe wall or vessel wall. { j PRIMARY CONTAINMENT INTEGRITY 1.33 PRIMARY CONTAINMENT INTEGRITY shall exist when: l l All containment penetrations required to be closed during accident j a. conditions are either: i j Capable of being closed by an OPERABLE containment automatic 1. isolation system, or Closed by at least one manual valve, blind flange, or deacti-l vated automatic._ valve secured in its closed position, except as 2. provided in Table 3.6.,4-1 of Specification 3.6.4. The containment equipment hatch is closed and sealed. b. Each containment air lock is in compliance with the requirements of c. Specification 3.6.1.3. The containment leakage rates are in compliance with the requirements d. of Specification 3.6.1.2. l L The suppression pool is in compliance with the requirements of e. ) Specification 3.6.3.1. 1 I 1-6 l' PERRY.- UNIT 1

n l l 3/4.3 INSTRUMENTATION j 3 '3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2. APPLICABILITY: As shown in Table 3.3.1-1. ACTION: a. With the number of OPERABLE channels less than required by the Minimum. OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition

• within I hour.

The provisions of Specification 3.0.4 are not applicable. b. With the number of OPERABLE channels less than required by the Minimum i OPERABLE Channels per Trip System requir'ement for both trip systems, place 4 at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1. SURVEILLANCE REQUIREMENTS ) 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1. 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and s'imulated automatic operation of all channels shall be performed at least once per 18 months. 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in' Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one chtanel per trip system such that all channels are tested at least once every 1 N times 18 months where N is the total number of redundant channels in a specific ~reactor trip system. "An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

• • The trip. system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the

~ trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip ) system in the tripped condition. , PERRY - UNIT 1 3/4.3 4 ~

Bj j l' t NO T 123 123 123 4 4 123 1 1 4 4 5 1 I C A )a S( LEM NE NT AS MHY UCS M IEP IBR 333 333 333 3 3 333 2 2 2 4 2 2 NLI MAT R N ER O PE I OP TA TN E M UR T S 1 N I 1 M 3 E L T EAS 3 S LNN Y BOO ) U E S AII d L CTT f I B N IAI 2 2 2 ) ) 2 2 A O LRD j 4 ) g T I PEN b b g I I T PPO ( C AOC 235 235 23S 1 1 i35 1 1 1 I 1 1 E TO R P ,~ l R h n a O w m w g ) o r o i e TCA C d e L H v l I t h e T a E V R

s r S r

o d l l o t e e e e n n th i h t h m v v o o i g n g a g o e e i i h ni o i l i D L L t t g oH M H u H a a' i M m m r r l i H e - ih a e e o d e g Sg e t t s a gx n x i x th a a I R nu e a u dH u e Sg W W e e e r al v R l e l v i u RF i F s-F i l H l l n n ' s t r a t e e e i i en a e n ir n a s-s s L L s t o r w o Be o r s s s e T ar e o r w r e ee e e m m r I it p P t wo t p Vr V3 V8 ae a P N du o u oP u o u er e U ee n e e l e n rs rl rl t u t l I g N F N I os oe oe Ss Sh l mN t e tv t v o g e L r a A e r cr ce ce nl ni w N t e aP aL aL iC iH y e e e a a r v I I a b A a b c d R R ' R M M D O n v T CN F 1 2 3 4 5 6 7 8 U kwk' E"e. i w'# w N !l lu

NO I 1 3 1 3 6 6 173 189 T CA = )a S( LEM NE NT MAS iHY 2 2 2 2 4 2 222 222 MCS N I O NEP I I LI T MBR A AT T R - N ER E PE ) M OP d U e R u T n S N i t I no M C E ~ ( T L S EAS 1 Y LNN .2) 2) ) ) 24 24 S BOO 9 9 h h 1 AI I .I ,f ( ( N CTT 1 S 1 S 1 l 135 135 3 O IAI I LRD 3 T PEN C PPO E E AOC L T B O w A R o T P ,L R e-O r T ue C sr A ou E R l s r e Cs n e r e w t r u t r o a e s sP d W t o a-t t s l F1 u e i e C 1 h m m h e0 S u s c v l n t l m h o a i e ae c V r w v Vt t T S l s i e a l y w ghl t V oS S rge a r aiv o p t p e m l o ni d a hHe T c L F t or on r I s-S CT Mo c i S N i e ee rt U Dl ea b n nv oi l i i l t s a L mv A ae b ba co u N rL r rV aP n O c u u e a I S T T R M J T C 3 N 0 1 2 U F 9 1 1 1 1 i k5 h5i w2 9w ~ l I

1 c, TABLE 3.3.1-1 (Continued) REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION Be in at least HOT SHUT 00WN within 12 hours. ACTION 1 _ Verify all-insertable control rods to be inserted in the core ACTION 2 and lock the reactor mode switch in the Shutdown position within one hour. Suspend all operations involving CORE ALTERATIONS

• and insert ACTION'3 all insertable control rods within one hour.

Be in at least STARTUP within 6 hours. ACTION 4 ) Be in STARTUP with the main steam line11 solation valves closed ACTION 5 wit.hin 6 hours or in at least HOT SHUTDOWN within 12 hours. ] Initiate a reduction in THERMAL POWER within 15 minutes and ACTION 6 reduce turbine first stage pressure to less than the automatic bypass setpoint within 2 hours. Verify all' insertable control rods to be inserted within one ACTION 7 hour. ) ACTION 8 Lock the reactor mode switch in the Shutdown position within i one hour. J Suspend all operations involving CORE ~ ALTERATIONS *, and insert a ACTION 9 all insertable control rods and lock the reactor mode switch in l the Shutdown position within one hour. l 4-9

• Except replacement of LPRM strings provided SRM instrumentation is OPERABLE

) per Specification 3.9.2. ,r e-g /. i:.l PERRY,AUNIT 1

3/4, M

________-___a

TABLE-3.3.1 (Continued)- -- ) ~ REACTOR PROTECTION SYSTEM INSTRUMENTATION-TABLE NOTATIONS '(a) A channel may be placed in an inoperable status for up to 2 hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter. (b) Unless~ adequate shutdown margin has been demonstrated per Specifica-tion 3.1.1 and the "one-rod-out" Refuel position interlock has been demonstrated OPERABLE per Specification 3.9.1, the shorting links shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn." (c) An.APRM' channel is inoperable if there are less than'2 LPRM inputs per-level or less than 14 LPRM inputs to an APRM channel. (d) This function is not required to be OPERABLE when the reactor pressure vessel: head'is removed per Specification 3.10.1. (e)' This function shall be automatically. bypassed when the reactor mode switch is not in the Run position. .p (f) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not. required. (g) With any~ control rod withdrawn. Not applicable to control rods removed l per Specification 3.9.10.1'or 3.9.10.2. (b) This function is automatically bypassed wherf turbine first stage pressure is less than the value of turbine first stage pressure corresponding to 40%** of RATED THERMAL POWER. l i

• Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
  • The initial-setpoint shall be < 25.4% of the calibrated span on ihcreasing turbine first stage pressure for AT (see 3/4.2.2 for definition) = 0* F;

< 21% for 0* F< AT < 50* F; < 18% for 50* F < AT < 100* F and < 15% for ~ 100* F< AT < 170* FT The alTowable value shall be < 26.9%, ~< 22.5%, ~< 19.5%, ~ ) and < 16.Sfrespectively. ~ PERRY _ -. UNIT.1 3/4 3-5 l

INSTRUMENTATION 3 3/4.3.2-ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION The isolation actuation instrumentation channels shown in Table 3.3.2-1 3.3.2 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME'as shown in Table 3.3.2-3. ' APPLICABILITY: As shown in Table 3.3.2-1. ACTION: With an isolation actuation instrumentation channel trip setpoint a. less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is-restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, With the number of OPERABLE channels less than required by the b. Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition

• within one hour.

The provisions of Specifica-l I tion 3.0.4 are not applicable. With the number of.0PERABLE channels less than required by the Minimum c. OPERABLE Channels per Trip Sy' stem requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1. E "An inoperable channel need not be placed in the tripped condition where this In these cases, the inoperable channel would cause the Trip Function to occur. shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

• • The trip system need not be placed in the tripped condition if this would i

When a trip system can be placed in the cause the Trip Function to occur. tripped condition without causing the Trip Functi.on to occur., place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip j system in the tripped condition. I ) 3/4 3-9 .. PERRY.- UNIT 1.

E z 4 i INSTRUMENT ATION- ) i i SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL-TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies st.own in Table 4.3.2.1-1, 4.3.2.2 - LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all. channels shall.be performed at least once per 18 months. l I 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per trip i system such that all channels are tested at least once every N times 18 months, j where N is the total number of redundant channels in a specific isolation trip -system. f ) i I ) ) PERRY - UNIT 1 3/4:3-10

NO I 0 0 1 0 2 0 3 4 3 3 3 T 2 2 2 2 2 2 2 2 2 2 2 C A ' L d d d d EAN n n n n 3 LNO a a a a BOI 3 AI T 3 3 3 3 3 3 3 CTI I AD LRN 2 2 2 2 2 2 2 2 2 2 PE0 AO1 PP 1 1 1 1 1 1 1 1 1 1 1 )a S( LEM NE NT e - AS n MHY i ) ) UCS l M 9 k / I EP f ( NLI 2 2 2 2 2 2 2 2 2 2 2 I BR MAT N R O ER I PE T

0. P A

T N E ) M U c R ( 1 T S ) S PY b 9, 2 N UB ( I O 9, 8, 3 RDL ) 7 N GEA 8, 8, c 3 O TN I EAG 7, 5, 5, ( ) ) E T VRI d b 2, ( L A LES 5, 2, ( A T VO 1 1 8 2 1 6 6 6 6 6 6 B U AP T C A N l l l O I e e e T N v v v A O e h l e e l l L I L g l L L wo e O T i e S A r H wm r N r L n I L e yu e O e n O t rn t I t uh S a D e a n T a T g TH W e l h W o A W h m i I i L eg e e u eH r dP g l ni nw n u n T l u n i l t O N e s atH e a S e iH io i c i - i E s2 s s s1 i I s1 L LL L a L L M s e t u-s t s h V e N el r na el i E el m m-mg mr mt eh n e n N Ve an a ai r au aa B p m x o "V I Ve P v I I v eo ee eH e et er T re l nEi re L re ti t r t s t a t e e A v N ol l i t oL l oL St Su S - n S r S p nT O t e aea t a M t a s e e u A c,. ni ns nw d np ne b e u w t gi c C c m i N aw y nrd aw n E aw id ie i o n i O Y eo r oua eo a T eo aa ar al o ae a I R RL D CPR RL M S RL MR MP MF C MT MA TL T A N C M I N I A F P a b c d e M a b c d e f U R P I R 2 T 1 M - g; yU (

N I 5 5 25 7 7 7 7 7 7 7 7 6 O T 2 2 22 2 2 2 2 2 2 2 2 2 AC L d EAN n LNO a AI T 3 3 3 3 3 3 3 3 3 3 3 3 BOI CTI I AD LRN 2 2 2 2 2 2 2 2 2 2 2 2 PEO AO 1 y 1* 1 1 1 1 1 1 1 1 1 PPC )a S( LEM NE N NT O AS I MHY T UCS A M d N NLI 2 7 22 1 1 1 1 2 1 1 1 2 EP ) T I e E I BR u M MAT n U R i R ER t T PE n S OP o N C I ( N 1 O I 2 TA S - 3 U PY T UB 3 C O ~ A RDL ) E GEA L N - TN c B O EAG ( ) ) A I VRI T T LES b N I ( O L VO 1 1 11 I 7 7 7 7 7 7 7 7 7 A AP T O A S L I O N S e l h r e g I O A u v i T h M t e H I A g E a L l l L i T r e-e O r2 H S e r n n S e Y p e ne n I tl S m h t ur uh ae n e g a T u T g n T Ov e o P T Ai W t i o U H ea eH n i N e r i E l L u t N a a l nr n o t M e s a A h e e-e i e i-i a N s, s i E g r r r s2 L p L t i e A A e s m e a t I sw e t L i A eo r i C H m r el me mr i i T VL P n i t t u Ve aT au t n N I R T n nt v e et i I E e ea re tt t a n O r-l C o l l T w w m mr ol S n S r I l tl e a A o o p pe t e e a ni np S u l l ih ip c Y ce w u W N R av y n F F ug um aw ib i m C n O A ee r a R qi qe eo am ae L a I D RL D M O a A EH ET RL MA MT S M T N T C O C N C A F S a b c R a b c d e f g h. E U E i v P I R 4 T 3 g j 't 0 p$ j m3 c$ t A 4 l

N O I 7 7 7 7 7 7 7 7 7 7 7 7 6 T 2 2 2 2 2 2 2 2 2 2 2 2 2 C A L EAN LNO AIT 3 3 3 3 3 3 3 3 3 3 3 3 3 BOI CTI I AD LRN 2 2 2 2 2 2 2 2 2 2 2 2 2 PEO PPC L 1 1 1 1 1 1 1 1 1 1 A0 1 1 )a S( LEM NE NT a a MAS e e UHY r r

• MCS A

A I / / NEP I LI 1 1 2 1 1 1 1 1 1 1 1 1 1 MBR AT N R O ER I PE T OP A ) T d N e E u M n U i R t T S N n S PY O o N UB I ) C I O T ) h k ( RDL A I ( N GEA L f 1 O TN O 9 9 9 9 9 9 9 ' 9 9 9 9 9 9 I EAG S 2 T .VRI I A LES 3 U AP M T VO E 3 C T A S E Y L N S h t B O g e n h t A I G i r h e g n h i e g T T N H u g i A I s i b H i i h L L s H m l l l b H g O O e A a e-e e m i S O w r t - n nh n A a w H I C o P s m m ne ng n o l ue oh oh ur ui u mh mh l N F y ar og og Tu TH Tr og og F O l h u Ri Ri t e oi oi e I e p xs H H ea e-em RH RH e r T n p E s t t nr n ni n u A i u e n-n- i e ie iT t - t - i s L L S er e e Lp L r L n n L s O nP me me m u e ee ee e S m m i pr pr me mt mr mr mr m r I a a bmiu i u aT aa au pu pu a P e e rg ut ut e er et it it e E t t ua qa qa tt t e t a ua ua t l R S S Tr E r E r Sn S p Sr qr qr S l O h e e e m e E e Ee r e C C C Cp Cp Cp ni ne np p p C e w u m R m R m I m y n N I I wI a I m I m ib iT i O R C C o Ci C e Ce am a ae H e H e Ci r I O R RL RD RT RT MA MaMT RT RT RT D M T T C C N A U E j F R a b. c 3. e f g h. k 1 i 'v P I R T 5 h=. c2 ~ w2 Y0

N O I 8 8 8 8 8 8 6 T 2 2 2 2 2 2 2 CA L EAN LNO BOI AIT 3 3 3 3 3 3 3 CTI I AD LRN 2 2 2 2 2 2 2 PEO PPC AO 1 1 1 1 1 1 1 )a S( LEM NE NT MAS UHY a a MCS e e r r I NEP A A I LI / / MBR 1 1 1 2 2 2 2 AT N R O ER I PE T OP A ) T d N e E u M n UR i t T S n S PY o N UB C I O ( RDL 4 4 ) 4 4 N GEA 5 f 1 O TN I EAG 3 3 9 3 4 1 3 2 T VRI A LES 3 U AP T VO 3 CA E L N n t B O i A I n T T e -t h A u-g i L b O m C i S A A r3 e H e e R r I ah ah n tl H u eg eg i ae R s n ri ri L Wv ( s e o N AH AH e e r i O m l l l r u t I t - t - a e eP s a T n n e s, s s i A ee ee th sw s) e t L mr mr S g eo ee r i VL Vv P n O pu pu i S it it CH i I I ua ua I r-rs l qr qr C - o os l l M E e E e R tl ti e a E p p / w ce cmh w u N T R m R m R o av arg y n O S H e H e Hl ee eei r a I Y RT RT RF RL RPH D M T S C N R e f g U H F R a b. ' c. d P I R T 6 hE c5w " R* T.% 1 ll 1 lIll ll lllllll

i i i TABLE 3.3.2-1 (Continued) I 1501ATION ACTUATION' INSTRUMENTATION ACTION ACTION 20 Be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTOOWN within the 'next 24 hours. ACTION 21 - Close the affected system isolation valve (s)'within one hour or: a. In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. b. In'0perational Condition *, suspend CORE ALTERATIONS, handling of irradiated fuel in th'e primary containment and operations with a potential for draining the reactor vessel. ACTION 22 Restore the manual initiation function to OPERABLE status within 48 hours or: In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT a. ( SHUTDOWN within the next 12 hours and in COLD SHUTDOWN I within the following 24 hours. i b. In OPERATIONAL CONDITION *, suspend CORE ALTERATIONS, operations with a potential for draining the reactor { vessel, and handling of irradiated fuel in the primary containment. ACTION 23 Be in at least STARTUP with the associated isolation valves' l ') closed within 6 hours or be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours. l ACTION 24 Be in at least STARTUP within 6 hours. ACTION 25 Verify ' SECONDARY CONTAINMENT INTEGRITY with the annulus exhaust - 4 gas treatment system operating within one hour. M ACTION 26 Restore the manual initiation function to OPERABLE status within 8 hours or close the affected system i, solation valves within I hour and declare the affected system inoperable.## j ACTION 27 Clo'se the affected system isniation valves within one hour and declare the affected system inoperable. N . ACTION 28 Within one hour lock the affected system isolation valves closed, or verify, by remote indication, that the valve (s)11s closed and electrically disarmed, or isolate the penetration (s) and declare the affected system inoperable. NOTES When handling irradiated fuel in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel. When any turbine stop valve is greater than 90% open and/or the key locked Condenser Low Vacuum Bypass Switch is in the normal position. 1 During CORE ALTERATIONS and operations with a potential for draining the ) . reactor vessel. The provisions of Specification 3.0.4 are not applicable. PERRY - UNIT I 3/4 3-15 ~ .. ). -

TABLE 3.3.2-1 (Continued) 3. ISOLATION ACTUATION INSTRUMENTATION ACTION NOTES (Continued) 4 (a). A channel may be placed in an inoperable status for up to 2 hours for ~ required surveillance without placing the trip system in the tripped con-dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter. (b) Also actuates the standby subsystem of the annulus exhaust gas treatment ~ system. (c) Also actuates the control room emergency filtration system in the recir-culation mode of operation. (d) - Also trips and isolates the mechanical vacuum pumps. (e) Closes only RWCU system isolation valve (s) 1G33-F004 (SLCS Pump A) and l 1G33-F001.(SLCS Pump B). (f) Manual initiation isolates 1E51-F064 and 1E51-F031 only and only following i manual or automatic initiation of the RCIC system. (g) Containment and Drywell Purge System inboard and outboard isolation valves each use a-separate two out of two isolation logic. (h) Requires RCIC system steam supply pressure - low coincident with drywell l l ). pressure high to isolate valve 1E51-F077. l(i) For this' signal, one trip s'ystem has two channels which close valves l 1E51-F063 and IE51-F076 while the other trip system has two channels l which close valve 1E51-F064. - l (j) Isolates both RHR and RCIC. (k) There is only one (1) RCIC manual initi.ation channel for valve group.9. l I PE;tRY - UNIT 1 3/4 3-16 j i f a

b r v e e v w o o g s ~b p H e a s s h e e l g s c g h h l i e n i c c ud s d h E 'i s r n n f n p i c F L p h i i u s n BE '6 / xo 0 p i 9 8 R 3 3 r AU WL 7 8 m 6 g 5 1 6 3 3 OA 2 4 4 .k 9 9 LV 1 1 4 1 1 3 c 7 1 7 1 L A a A 3 1 N 1 5b 3 5 3 d d n S n u T u o N o r I r g O g k m P k c u T c a u O v w E a b c S b a r v N e e I o o g T s b p H A T e a s s 2 T N h e e l g s N I c g h h l i e 2 E O n i c c u s d h M P i s r n n f p i c F 3 U T p h i i s n R E 8 / x 0 p i 4 8 R 5 5 3 T S S 9 6 m 6. 0 7 3 5 1 E N P. 2 6 1 L I I 1 1 2 1 1 3. 0 8 1 8 1 8 B R A A N T 3 3 N 3 $ 1 5 T O I TAU T C A h N h g w O g i I ei H o T gH L A r h L l u-l l g O e P e e n i S N v n v v o e H I O e h l o e e i r I L g l i L L t u w l l T i et a s o e A r H wa r N r i s w L n n L e yi e O e d e o n n O t rd t I t a r l uh u S a Da a n T a R P F T g T i I W e R W o A W m r d i L e e e u eH e l u nm l t O l n n n u n n TN e s au e a S e i i i c i-i E s2 s n s1 i I s1 L L L a L L M s e t e s t s V e N el r nl el i E el m m m mr m I Ve P eP Ve n N Ve a a a r au a A v m v I I v e e e e et e T re l nt re L re t t t s t a t N oL l i s oL l ol S S S n S r S O t e au t a M t e e u A c, n n n d np n w t a c C c i i i n im i N aw y nh a w n E aw O Y eo r ox eo a T eo a a a o ae a I R RL D CE RL M S RL M M M C MT M T A C M N N I I A U R F P a b c d. M a b c d e f. g e P w I R T 1 2 t* jd oE7,S i i i i'

l INSTRUMENTATION 1 4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS j l LIMITING CONDITION FOR OPERATION 3.3.7.4 The remote shutdown system instrumentation and controls shown in Table 3.3.7.4-1 shall be OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2. j i ACTION: With the number of OPERABLE remote shutdown system instrumentation a. channels less than reouired by Table 3.3.7.4-1, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours. b. With the number of OPERABLE remote shutdown system controls less than required in Table 3.3.7.4-1, restore the inoperable control (s) to OPERABLE status within 7 days or be in at least HOT SHLT00WN within the next 12 hours. The provisions of Specification 3.0.4 are.not applicable. c. ) l SURVEILLANCE REQU]REMENTS 4.3.7.4.1 Each of the above required remote shutdown system instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK i and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.4-1. 4.3.7.4.2 Each of the above remote shutdown controls shall be demonstrated OPERABLE by verifying its capability to perform its intended function (s) at least once per 18 months. PERRY - UNIT 1 3/4 3-73 J

TABLE 3.3.7.4-1 l' REMOTE'SHUTOOWN SYSTEM INSTRUMENTATION MINIMUM CHANNELS OPERABLE INSTRUMENT Division 1 Division 2 1. Reactor. Vessel Pressure l' 1 '2. Reactor Vessel Water Level '1 -1 3. Safety / Relief Valve Position *, 3 valves. 1/ valve-1/ valve-4. ' Suppression Pool Water Level 1 1 5. Suppression Pool Water Temperature 1 1 1 6. Drywell Pressure 1-1- 7. Drywell Temperature-1

• 1 j

E. RHR System Flow 1 1 9. Emergency Service Water Flow to RHR 1 1 Heat Exchanger 10. Emergency Service Water Flow to 1 1 Emergency Closed Cooling Heat Exchanger 11. RCIC' System Flow 1 NA 12. RCIC-Turbine Speed. '1 NA. i 13. Emergency Closed Cooling 1 1 System Flow 14. Inboard MSIV Position *", 4 valves NA 1

• Indicating lights to indicate valve solenoid energized /de-energized.
  • Indicating lights to indicate valve position.

PERRY - UNIT 1 3/4 3-74

p* q Liu ) LTABLE'3.3.7.4-1 (Continued) p REMOTE SHUTDOWN SYSTEM CONTROLS. 1: MINIMUM CHANNELS OPERABLE y .CONTROJ. Division 11 0ivision 2 l ~ lESW Pump. .- 1 'I ESW Pump Discharge Valve 1(a) 1 'RHR'HX's Inlet / outlet / Bypass Valves. 3(a) 2((a) RHR HX's ESW Inlet /0utlet Valves 2 a) 3 RHR Pump 1 1 RHR to Containment Shutoff-Valve 1 1 RHR Pump Suppression Pool Suction Valve 1 1 .LPCI Injection Valve I 1 RHR A1 Shutdown Cooling Suction Valve 1 NA RHR Upper Pool cooling Isolation Valve 1 1 RHR Head Spray Isolation Valve 1 NA RHR HX's Dump Valve Containment Spray First Shutoff. I 1 l' 1 Shutdown. Cooling to Feedwater Shutoff 'l 1 RHR. Test Valve to Suppression Pool-I 1 Shutdown Cooling Outboard Suction Isolation Valve 1-HA RHR A to Radwaste Second Isolation Valve 1 NA 4 ' Steam Condensing Shutoff Valve to RCIC 1 1 RHR HX's' Steam Shutoff Valve 1 1 1 RHR Pump Minimum Flow Valve 1 _1 4 ECC Pump I 1 RCIC Turbine Gland Seal Compressor 1 NA j .RHR & RCIC Steam Supply Outboard Isolation Valve 1 NA RCIC Second Test Valve.to CST 1 NA .{ RCIC Turbine Trip 1 NA i RCIC Steam Shutoff Valve 1 'NA RCIC First Test Valve to' CST-1 NA I l RCIC Pump CST Suction Valve 1 NA RCIC" Injection.. Valve 1 NA RCIC Pump Suppression Pool Suction Isolation' Valve 1 NA j RCIC Turbine Trip Throttle Valve 1 NA 1 RCIC Pump Minimum Flow Valve 1 NA 1 RCIC' Turbine Exhaust Shutoff Valve 1 NA i RCIC Exhaust Vacuum' Breaker Outboard Isolation Valve. I NA 'l RCIC Pump' Discharge to L.O. Cooler Valve 1 NA RCIC Exhaust Vacuum Breaker Inboard Isolation Valve NA 1* RHR 8 Shutdown Cooling Suction Valve-NA 1* Shutdown Cooling Inb'oard Suction Isolation Valve NA 1* RHR & RCIC Steam Supply Inboard Isolation Valve NA 1* RHR & RCIC Steam Supply Warmup I. solation Valve N l 4 Safety Relief Valves 3g) 3y) ) Control Room to Shutdown Panel Transfer Switches 14,(b) 2* I ) l APRM' Power Supply Breakers la y Inboard Main Steam Isolation Valve NA 2 Diesel Generator Room Fan IA Temperature Controller 1 NA (a) 1 per valve-(b) One breaker constitutes one channel for ATWS Division 1 and Division 2. -f 4 (c) One' switch for Solenoid "A" per 4 valves, one switch for Solenoid "B" per 4 valves. ~

• These Division 2 controls are physically located on the Division 1 panel.
  • These breakers are physically located on ATWS Distribution Panels 1R14-5014 and 1R14-S015.

PERRY - UNIT 1 3/4 3-75 0

l TAELE 4.3.7.4-1 ' REMOTE SHUTCOWN SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ) CHANNEL CHANNEL INSTRUMENT ' CHECK ' CALIBRATION 1. Reactor Vessel Pressure M R 2. Reactor Vessel Water Level M R l 3. Safety / Relief Valve Position M NA l 4. Suppression Pool Water Level M R a 5. Suppression. Pool Water Temperature M R' 6. Drywell Pressure M R 7. Drywell Temperature M R 8. RHR System Flow M R 1 9. Emergency Service Water Fiow to RHR M R Heat Exchanger -j t c. ~I z

10. - Emergency Service Water Flow to Emergency M

R- )_ - Closed Cooling Heat Exchanger

11. _RCIC System Flon H

R j 12. RCIC Turbine Speed M R 13. Emergency Closed Cooling System Flow M R 14. Inboard MSIV Position M NA -l i s PERRY - UNIT l' 3/4 3-76--

LyuAuun anu.i CWcle effici o(Ctwork f o as y a s/t M )/(Ene w in s = Vet + 5 atg e. og, E. set-A = xW A = Age ht gE'= 5 av2 a=(Vt-Vo)/t l PE = ogh x = an2/ts = o.693/tg vg = Vo + at = = e/t u..F geff=((4)(4)3 I(4)+-(4)] d = 931 am i,g,,-zx 6=& coat I = lo *

• l e

6 = uAst I = lo to-*/I" .Pwr = vfah TYL = 1.3h P. Po10sur(t) HVL = -0.693A-P m.P et/T SCR = S/(1 - K,ff) l o SUR = 26.06/T CRx = S/(1 - Keffx) CR (1 - K,ffg) = CR (1 - keff2) l 3 2 . SUR = 26p/a* + ( 6 p )T M = 1/(1$ - Keff) s' CRg/CRo l T = (a*/p) + [(a - p)/Ip) .M = (1 - Keffo)/(1 - Keff t) T = a/(p - s) SOM = (1 - K,ff)/Keff I . T = (s - p)/(Ap) a* = 10-5 seconds e = (Keff-1)/Keff = ekeff/Keff i = 0.1 seconds *1 ~ p = [(a /(T Keff)3 +..[ieff/(1 + IT)) 'Ijdt=1d22 2 P = (reV)/(3 x 1010) It t 2=1d22 d 2 R/hr = (0.5 CE)/d (meters) 2 =.N R/hr = 6 CE/d2 (feet) Miscellaneous Conversions l I' Water Parameters 1 1 curie = 3.7 x 1010dps l l' 1 gal. = 8.345 lbm. 1 kg = 2.21 the j 3 Btu /hr i 1 gal. = 3.78 liters 1 hp = 2.54 x 10 6 1 ft3 = 7.48 gale'.' 1 aw = 3.41 x 10 Stu/hr Density = 62.4 lbm/ft 1 in = 2.54 cm Density = 1 gn/cm3 'F = 9/5'C + 32 l heat of vaporization = 970 Btu /1bm

• C = $/9 (*F-32)

I i Heat of fusion = 144 Btu /1be 1 BTU = 778 ft-1bf 1 Ata = 14.7 psi = 29.9 in. Hg. 1 ft H 0 = 0.433 lbf/in2 l 2

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i

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==~c qw \\g l m ~T 2 ~~~ 55;; ~ w ~ =- m_~ ~ ~ I ~ ~ "w s er M% 6Q N w -~ ~ --~~_ _=:== -sii;;;y =p --======== j gi a> o a t i g '"300 W aw g _ not ye \\, =1 d'"I" 1 s_ i n i i n i i n at T i i I' F4 1 7. _ ; _ T_., chaft.

34 mess /Thorseat7ssemia atsenem ~ siens: m einewwe seiem tendes and Fis. I has been ametrocnes emm 7nwmeernemic and r,wepw rw pwtes er Basem (oseyright.1967. by be Amortcon society et taschencer Ergmeers.) l taw 1 t Properties of saturated steam and saturated water (umperature) -a Entropy. Stu/Ib : F Volume, ft'/lb Enthalpy, Stu/lb Wekt Evap Steam Water Evep Steam Water Evap Seaem A A A s, sg s, 's 'e 's f 4 s4 at 0.08859 OD1602 3305 3305 -0.02 1075.5 107M 0.0000 2.1873 2.1873 32 35 0.09791 041602 2948 2948 3.00 10732 1076.8 0.0061 2.1706 2.1767 35 40 032163 0D1602 2446 2446 8.03 1071.0 1079.0 0.0162 2.1432 2.1594 40 45 0.14744 041602 2037.7 2037E 13.04 1068.1 1081.2 0.0262 2.1164 2.1426 45 to 0.17796 OD1602 1704.8 1704.8 18.05 1065.3 1003.4 0.0361 2.0901 2.1262 50 60 02561 0D1603 1207.6 1207.6 28.06 1059.7 1087.7 0.0555 2.0391 2.0946 60 70 0.3629 0D1605 868 3 868 4 38 45 105f2.0 1092.1 0.0745 1.9900 2.0645 70 to 0.5068 0.01607 6333 633.3 48.04 1048.4 1096.4 0.0932 1.9426 2.0359 to 90 0.6981 0D1610 468.1 468.1 58 M 1042.7 1100.8 0.1115 1.8970 2.0086 90 100 0.9492 0D1613 350.4 350 4 6840 1037.1 1105.1 0.1295 12530 1.9825 100 b 110 1.2750 0D16174 265.4 265.4 ??_98 1031.4 1109.3 0.1472 1.8105 1.9577 110 120 1.6927 0D1620 203.25 203.26 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 e' 130 2.2230 DD1625 157.32 15733 97.96 1013.t 1117.8 0.d817 1.7295 1.9112 130 T 140 2.8892 0D1629 122.98 123.00 107.95 10140 1122.0 0.1985 1.6910 1.8895 140 150 3.718 041634 97.05 97.07 117.95 1008.2 1126.1 0.2150 1.6536 1.8686 150 160 4.741 CD1640 7727 7729 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 170 5.993 0.01645 62.04 62.06 137.97 996.2 1134.2 0.2473 1.5822 1.8295 170 180 7.511 041651 50.21 50.22 148.00 990.2 1138.2 02631 1.5480 1.8111 100 190 9340 CD1657 40.94 40.96 158.04 964.1 1142.1 0.2787 1.5148 1.7934 190 300 12.526 0.01664 33.62 33.64 168.09 977.9 1146.0 0.2940 1.4824 1.7764 200 210 14.123 OD1671 27.80 27.82 178.15 971.6 1149.7 03091 1.4509 1.7600 210 212 14.6 % 0.01672 26.78 26.80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 220 17.186 OD1678 23.13 23.15 188.23 965.2 1153 4 0.3241 1.4201 1.7442 120 230 20.779 CD1685 19364 19.381 198.33 958.7 1157.1 0.3388 13902 1.7290 130 240 24.968 OD1693 16.304 16.121 200 45 952.1 -1160.6 03533 13609 1.7142 340 250 29 825 CD1701 13.802 13C19 ' 218.59 945.4 1164.0 03677 1.3323 1.7000 250 260 35 427 0D1709 11.745 11.762 1'28 76 938.6 1167.4 0.3819 1.3043 1.6862 260 270 41.856 0D1718 10.042 10.060 238.95 931.7 1170.6 0.39 0 1.2769 1.6729 270 280 49.200 0.01726 8.627 8.644 249.17 924.6 1173.8 0.4098 12501 1.6599 280 290 57.550 CD1736 7.443 7.460 259.4 917.4 1176.8 0.4236 12238 1.6473 290 l 300 67.005 0D1745 6.448 6.466 269.7 910.0 1179.7l 0.4372 1.1979 1.6351 300 310 77.67 OD1755 5.609 5.626 280.0 902.5 1182.5' O.4506 1.1726 1.6232 310 220 89.64 0.01766 4.896 4.914 290 4 894.8 1185.2 0.4640 1.1477 1.6116 820 540 117.99 d OD1787 3.770 .5.788 311.3 878.8 1190.1 OA902 1.0990 1.5892 340 360 15341 '!CD1811 2.939 2.957 332.3 862.1 1194.4 03161 1.0517 1.5678 360 300 195.73 CD1836 2.317 2.335 353.6 844.5 1198.0 O/A16 1.0157 1.5473 300 400 247.26 0D1864 1.8444 1 A630 375.1 015.9 1201.0 0.5647 0.9607 1.5274 400 420 308.78 OD1894 1.4808 1.4997 396.9 SG6.1 1203.1 0.5915 0.9165 1.5080 420 440 381.54 0D1926 1.1976 1.2169 419.0 785.4 1204.4 0.6161 0.8729 1.4890 440 460 466.9 CD1% 0.9746 0.9942 441.5 763.2 1204.8 0.6405 C&99 1,4704 460 400 565.2 0B200 0.7972 0.8172 464.5 739.6 1204 1 0.6684 0.7871 1.4518 480 $00 680.9 0D204 0.6545 06749 487.9 714.3 1202.? 0.6890 0.7443 1.4333 500 Sto , 81.2.5 CD209 0.5386 0.55 % 512.0 687.0 1199.0 0.7133 0.'7013 1.4146 520 540 94 2.8 0.0215 0.4437 0.4651 536.8 657.5 11943 0.7378 0.6577 1.3954 540 560 1133.4 CD221 . 0.3651 0.3871 562.4 625.3 1187.7 0.7625 - 0.6132 1.3757 560 S40 1326.2 CD228 02994 0.3222 589.1 589.9 1179.0 0.7876 0.5673 13550 580 800 1543.2 0 2236 0.2438 0.2675 617.1 550.6 1167.7 0.8134 0.5196 1.3330 600 420 1786.9 CD247 0.1 % 2 0.2208 646.9 506.3 1153.2 4 0.8403 0.4689 1.3092 620 440 2059.9 02260 0.1543 0.1802 679.1 454.6 1133.7 08686 0.4134 12821 440 660 2365.7 0D277 0.1166 0.1443 714.9 392.1 1107.0 04995 0.3502 1.2498 660 000 2708.6 02304 0.0808 0.1112 758.5 310.1 1068.5 0.9365 0.2720 12086 Geo 700 3094.3 CD366 0.0386 0.0752 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 Q3 EDS NE .e GSO 906.0 0 906.0 1D612 0 1D612 705.5 l

a4 TsNe 2 l Properties of satursted steam and saturated water (pressure) Vokme ftVib Lcth14 8tu/lb Entropy. Stu/lb a F twry. Stu/lb Pet Y' m ater Evep hm Water Evsp steam ' Weter Even suam Water Stum 't 't 'a f e

1. s s,

s 4, e, u, A A g [ 0134G 32.018 CD1602 33023 3302.4 0.00 1075.5 1075.5 'O 2.1872 2.1872 0 10213 0.0806 0.10 35.023 CJ01602 2945.i 2945.5 3.03 1073.8 1076.8 0.0C61 2.1705 2.1766 3.03 1022.3 0.10 C 15 45 453 CD1602 2004.7 2004.7 13.50 1067.9 1081.4 02271 2.1140 2.1411 13.50 1025.7 0.15 4.20 $3.160 CD1603 15263 15263 21.22 1063.5 1084.7 0.0422 2.0738 2.1160 21.22 1028.3 OJO 14 64.484 0.01604 1039.7 1039.7 32.54 1057.1 1089.7 0D641 24168 2.0809 32.54 1032.0 0.30 l 0.40 72149 041636 7920 792.1 40.92 1052.4 1093.3 0.0799 1.9762 2.0562 40.92 1034.7 0.40 ) 0.30 l 0.5 O 79.586 0 01607 6415 641.5 47.62 1048 6 1096.3 04925 13446 2.0370 4742 1036.9 03 f { 0.6 85.218 0.01609 540.0 540.1 5325 1045.5 1098.7 0.1028 1.9186 2.0215 5324 1030.7 0.6 0.7 l 90 09 0 01610 466 93 466 94 58.10 1042.7 1100.8 03 12966 2.0083 58.10 1040.3 0.7 1 02 94 38 0.01611 411.67 411.69 6239 1040.3 1102.6 0.1117 12775 1.9970 6239 1041.7 (La 09 9824 0 01612 368 41 368 43 66.24 1038.1 1104.3 0.1264 12606 1.9870 6624 1042.9 03 ( 1.0 - .101.74 001614 333.59 333 60 69.73 1036.1 1105.8 0.1326 1E455 1.9781 69.73 1044.1 1A 2.0 126 07 0 01623 173 74 173.76 94.03 1022.1 1116 2 0.1750 1.7450 1.9200 94 03 10512 lLC 3.0 141.4' O.01630 118.71 118.73 109.42 10132 1122.6 02009 1.6854 1386: 109 41 1056.7 Ab f of 152.96 0.01636 9043 90 64 120.92 10064 1127.3 0.2199 1.6428 1A626 12030 1060.2 4A k.0 16224 0.01641 73.515 73 53 130.20 1000.9 1131.1 02349 1.6094 13443 130.18 1063.1 1.0 l 6.0 170.05 001645 61 967 6198 138.03 9962 11342 0.2474 1.5820 12294 138 01 1065.4 Lo 7.0 176 54 0.01649 53434 53 65 144.83 992.1 1136.9 02581 1.5587 12168 144.81 1067.4 7A 4.0 182A6 0.01653 47.328 47.35 150.87 988.5 1139.3 02676 15384 13060 150 34 1069.2 SA 9.0 188.27 0.01656 42385 42.40 156.30 985.1 1141.4 02760 15204 1.7964 156.28 1070.8 94 10 19321 0 01659 38.404 38 42 161.26 932.1 1143 3 02836 15043 1.7879 161.23 1072.3 10 14.696 212.00 0.01672 26.782 2680 !&O 17 p70.3 1150.5 0.3121 1.4447 1.7 % 8 180.12 1077.6 14.696 i 15 213.03 0.01673 26.274 2629 1'81.21 969.7 1150.9 03137 1.4415 1.7552 181.16 1077.9 13 20 227.% 0.01683 20.070 20 087 196.27 960.1 1156.3 0.3358 1J%2 1.7320 196.21 1082.0 20 j 30 25034 0.01701 13.7266 13.74c ' 218.9 945 2 1164.1 0.3682 1.3313 1.6995 218.8 1087.9 30 J 40 26725 0.01715 10.4794 10 497 ?36.1 933 6 11693 0.3921 12844 1.6765 236.0 1092.1 40 i 923.9 1174.1 0.4V12 1.2474 16586 250.1 1095.3 50 50 281 02 0 01727 84967 8.514 ; 250.2 60 292.71 0.01738 7.1562 7.174 ] 262.2 915.4 u77 <6 0 4273 12167 1.6440 262.0 1098 0 60 1 s 70 302.93 0.01748 6.1875 6205 ' 272.7 90;.8 1180.6 0.4411 1.1905 14316 272.5 1100.2 70 30 312.04 9.01757 5.4536 5.471 282.1 900 9 1183.1 0.4534 1.1675 14208 231.9 1102.1 80 30 320.28 0.01766 42777 4295 290.7 894.6' 1185.3 0 4643 1.1470 1.6113 290 4 1103.7 90 ? 100 327A2 0.01774 4 4133 4.431 298.5 888 6 1187.2 0 4743 1.1284 1.6027 298 2 1105.2 103 ! 120 341.27 0.01789 3.7097 3.728 312 6 877.8 1190 4 0 4919 1.0960 1.5879 312.2 1107.6 120 l 140 353 04 0.01803 32010 3.219 325.0 868.0 1193 0 05071 1.0681 1.5752 324.5 1109.6 1A0 l 160 363 55 0 41815 22155 2E34 336.1 859.0 3195.1 03206 1.0435 1.5641 335.5 1111.2 360 l 130 373 08 0.01827 25129 2 531 34f 2 850.7 1196.9 05328 1.0215 15543 345.6 11125 120 l 200 38130 0.01839 22689 2287 355.5 842.8 1190.3 ctOS.1.0016 15454 154 S 1113.7 200 l \\ 250 400 97 0.01865 1 2245 18432 376.1 Bhc 1201.1 05679 0.9585 1.5264 3753 1115.8 250 x s 1.5238 1.5427 394.0 808.9 1202 9 0.5882 0.9223 1.5105 392.9 1117.2 300 1.3064 1.3255 409.8 794.2 1204.0 0.6059 0.8909 1.4968 408 6 1118.1 350 300 417.35 0.0188i( 40C 444.60 0.0193 1.14162 1.1610 4242 7804 1204.6 0 4217 03630 1.4847 422 7 1118.7 400, 350 431.73 0.01913 450 456.26 > 0.0195 141224 1.0318 437.3 767.5 1204.8 0.6360 0 8378 1.4738 435.7 1118.9 450 l Y 500 467.01 0.0198 0 90787 0.9276 449.5 755.1 1204.7 0.6490 0.8148 1.4639 447.7 1118.8 ! loo ! 550 476.94 0.0199 0.82183 0 S418 4(A9 743.3 1204.3 0.6611 0.7936 1.4547 458.9 1118 6 550' 600 486 20 0 0201 0.74 % 2 0.7698 471.7 732.0 1203.7 0 6723 0.7738 1.4461 469 5 1118.2 600, 700 503.08 0.0205 0.63505 0.65 % 491.6 710.2 12012 0 6928 07377 1.4304 488.9 1116.9 700: 800 518.21 0.0209 054809 05690 509.8 689 6 1199.4 0.7111 0.7051 1.4163 506.7 1115.2 000 I 0 0 0212 0.47968 03009 526.7 669.7 11964 0.7279 04753 1.40M ' 523 2 11130 EM l 2000 544.58 0.0216 0 42436 0.4460 542.6 650 4 1192.9 0.7434 06476 139m '5396 11104 100t 900 E31.95 1100 55628 0.0220 037863 0.4006 557.5 631.5 1189.1 0.7578 0 6216 ' t.3794 553.1 1107 5 110C l 1200 % 7.19 0.0223 034013 03625 571.9 613.0 7184.8 0.7714 05%9 13683 566.9 1104.3 120( l 1300 577.42 0.0227 0 30722 03299 585.6 594 L ' M0.0 02843 05733 1 3577 530.1 11009 130(l l 576 5 1175.) 13474 592 9 1097.1 558 4 1170A ;j 0.7%6 0.5507 1400 587.07 0.0231 0.27871 03018 598.8 d2085 05288 13373 605.2 1093.1 ou-2000 635 30 0 0257 0.16266 01883 672.1 466 2 1138.3 046'15 0 4256 12881 662 6 1068 6 200; 1500 596 20 0 0235 0 25372 02772 611.7 2500 666 11 0.0286 010209 01307 731.7 361.6 1093.3 0.9139 0.3206 1.2 345 718.5 1032.9 250I 3000 695.33 0.0343 0.05073 ,0.0850 801 A 218f 1020 1-0.9728 0.1851 1.1619 782A 972.1 300l 320L3 705 47 0.0508 4 0.0508 906.0 0 906.0 1.0612 0 1.0612 8751 875.9 32C i

.w 4 Tehle 3 Properties'et supertiested steam Cad 4.M water pomperstwo asad pressure) Tesapershot,F gest.assne) 100 Joo 300 400 soo 400 700 soo 400 1000 1100 1300 1300 3400 tsoo Ahs potes. I i -evet n. e 0D161f 3B23 4623 611S 873 4 631.1 000.7 1150 2 3195J 1241A 1208 6 1336.1 1384.5 2.2708 2J144 197J0 200 62 22153 233 45 2m06 2.1152 2.1722 22237 3 8 G8.00 9024 HI224 11421 126 15 138.08 150.01 161.M 173.86 1 1639.6 1993J 1748.0 1803 5 0 01.74) s 0.1295 IIMA 12412 1298.2 13353 1384.3 1433.6 14831 15M J 66 ' 221M 23509 2.3811 2A101 e OA161 78.14 3 3369 1.9943 2.0460 2.0932 2.1369 2.1776 22159 2.2521 5 6 6801 1148 6 e 04161 38A4: 44 9il 5123 57.04 43.03 69.00 74.98 00 (162.24) s 0.1295 13716 1335.5 1384.0 1433.4 1483 5 1534 6 1586.6 2.1757 2.2101 2.2430 2.2744 2 3046 2 30 6 88.02 1146 6 1103 7 1240.6 1287A1 3692 2 4166 2.0603 2.1011 2.1394 53H6 57326 61305 65282 69258 73A33 (193.21) s 0.1295 i1.7928 12593 13173 1383.8 14332 1483 4 1534.5 1586 5 1639 021M J 29.999 33 M3 37.985 41386 45378 49.964 1.2599 2.2090 2.0155 2.0%3 2.0946 2.1309 2.1M3 2.1982 2.229 38 6 68 04.168.09 1192.5 1239 3 1287.3 1335.2 v 0.0161 (213.03) s 0.1295 02 HO1A134 12720 13242 1.9717 37.458 40.447 43435 46 420 49 A05 il2.3 1534.3 1586.3 16393 16931 1747A 180 31 A66 34 465 22572 22 3 % 25 428 28 457 2.0991 2.11M 2.1M5 2.1979 2.2282 30 6 68 05 168.11 1191.4 12392 1286S 1334.9 1383.5 1432.9 14&3.2 , 00161 0.01M Q27.95) s 01295 0 29401.7835 1A397 1A921 IS397 1 A836 2.0244 2A628 v 0.0161 0.0166 11.036 12.624 14.165 15.685 17.125 18.699 40 4 68.10 168 15 1186 6 12M 4 1285.0 1333 6 1382.5 1432.1 (267.25) s 0.1295 0 29401.6992 13608 1 4143 1A624 1.9065 1.M76 , 0.0161 0.01% 7.257 8.354 9.400 10 425 11.438 12 446 13 1585.3 1638 4 1692 4 1747.1 1802A 68 15 16820 1181.6 1233.5 1283.2 1332.3 1381.5 1431.3 14812 15332 2.0120 2.0450 2.0765 2.1068 2.1359 1.7134 1.7681 1A168 1A612 1.9024 13410 13774 0.1295 0.2939, 1.6492 9.319 10.0M 10A29 11.581 12311 13.08 00 6 68.21 16824 269.74 12305 1281.3 1330.9 1 (292J1) s 0.0161 0.0166 0.0175 t 6.218 7418 7394 8.560 I/4790 1.7349 11842 1A289 IJ702 13089 1 4.935 5.588 6.216 6 833 7A43 8.050 8.655 9 30 4 0.1295 0JB39 04371 1637.6 1691.6 1746.5 18022 Q12.04) s 100 6 6826 168 29 26917 1227.4 1279 3 1329 6 1379.5 1429.7 1480 4 1532.0 158 0.0161 0.01 % 0.0175 1 3083 2.0199 2.0502 2.0794 i 027A2)s 0 1295 02939 0.4371 1A516 1J088 13586 1.8036 1A451 1A839 13205 19552 e 92130 6 1928 6 7006 7 2060 7.7096 8 2119 4 713 1691.3 17462 1802.0 1637.1 0.0161 0 0166 0.0175 4.0785 4 6341 5.1637 5.6831 320 6 68.31 168 33 269.81 1224 1' 1277 4 1328.1 1378 4 1428 8 1479.8 1531A 15 1.9680 1.9996 2.0300 2.0592 4 041.27) s 0.1295 0 2939 0 4371 1.6286 1.6872 1.7376 IJ829 1 3246 12635 1.9001 1334 i e 460M 7.0349 7A652 72946 8.3233 340 6 6837 168 38 269 85 1220.8 12753 1326.8 1377 A 1428.0 1419 6.1709 3 9526 4 4119 4 2585' 5 2995 5 3364 0 53.04) s 0.1295 02939 0.4370 1.6085 1.6686 1.7196 13652 12071 1A461 0 0161 0.01 % 0.0175 34661 = 5.7741 6.1522 4.5293 6.9055 7.28 360 6 M 42 168 42 269A9 1217 4 1273 3 1325 4 1376 4 1427.2 147 3 A480 4.2420 4 6295 54132 53945 i 0 63.55) s 0.1294 02938 OA370 1.5906 1.6522 13039 1J499 11919 1 A31 0.0161 0.01% 0.01M 3.0060 3 4413 e 4.1084 4.4505 4 1907 5.1299 5 4657 5 300 6 68 47 168 47 269 92 1213A 1271.2 1324 0 1375.3 1426.3 147 3.0433 3 4093 3.7621 14900 1J362 IJ784 1A176 13545 12894 1 32 0.0161 0 21 % 0.0174 2 6474 5.5209 5A21 e (373.08) s 0.1294 0R38 04270 1.5743 1.6376 3D583 33783 3.6915 4.0008 43077 4.6128 4.9 300 6 68 52 168 51 269 96 1210 1 1269 0 1322 R2938. 04369 i l.5593 14242 1.6776 IJ239 0.0161 0.01 % 0 4174 23598 21247 - e 3 S278 4.1709 4 4131 4.654 24872 2.M10 3.1909 3 4382 34837 081AO) s 0.1294 14753 1527.6 1580.6 16344 1688 9 e 00161 O DI M 04174 04186 f 2.1504 2.a662 s 0.1294 0.2937 04368 0.56671.5961 1.6502 1.6976 1J405 11801 1A1 l 290 6 68 66 16B 63 270.05 375.10 1263 5 1319 0 1371.6 1423 4 3 6746 3A764 ' 2.6509 2A585 3.0643 32688 34721 68 79 168 14 270 14 3M.151257.7 1315.2 1368 9 14213 1473.6 15 (400 97) 0.0186 1J665 2.0044 2.2263 2A407 0.12M 0.2937 C 4307 0.56651.5703 1.6274 14758 1J192 13591 119 0 0161 0 01M. 0 0174 1 e 2 4445 24219 23980 23730 3.1 300 6 00161 021M 0.0174 0.01861A913 1.7028 1 A970 2.0832 2.2652 1578.2 16323 1687.1 1742 6 (417.35)s 1.Mor 68 92 36885 UO24 3 4.21 1251.5 1311 4 13662 1419 2 1471A 1524.7 1 A477 1 A798 13',05 1.5483 1.6077 14571 13009 1J411.1J787 13141 2.2901 2A450 2.590 21515 1 390 6 0.1293 0J936 04M7 0.5M4 168 97 270.33.3M.27 1245.1 1307 4 iM34 14174 1470.1 1523 0 0162 1.2841 1.4763 1.6499 1A151 1.9 4 9. 2.1339 (431.73)s 1.5282 1.5901 1.6406 14850 1J255 116 00161 0_01M 0.0174 e 04186 0.9919 1.1584 1.3037 1 4397 1.5 69.05 0.1293 02935 OA3M 0.%63 400 6 1629.1 16644 1740 3 1796 (444 60) e 69.32 169.19 270 51 3M 3f 1231.2 1299.1 1357.7 141 1J9' 3 0.566011A921 1.5595 1.6123 14678 14990 IJ371 IJ7 00161 OD166 0.0174 i 300 6 0 1292 02934 0 4364 (467.01)e .s

~_ Table 3 Properties of superbested steem cod compre8 sed water (temperature aM preeBure) i ano poen. Tempween.J l Wet in. (estmap) 100 300 300 400 900 000 700 000 000 1000 1100 1200 1300 1400 1g00 e 0.0161 0.0166 0.0174 0.0186 0 7944 0.94 % 1.0726 1.1992 1.3008 1A093 13160 1A211 1 1252 122S4 1.9309 000 6 69.58 19042 27030 375.49 1215.9 1290.3 1351A 1408.3 1463 0 1517.4 1571.9 1627.0 1826 1738A 17956 (486.20) s 0.1292 OJ913 0.4362 0.5657 1.4590 1.5329 1.5444 14351 1.6769 IJ155 1J517 1.7859 12184 1A494 1A792 e 0.0161 0.0166 0.0174 0.0186 0.0204 CJ928 0.9072 1A102 1.1078 12023 12948 12858 1A757 1.5647 1A630 700 8 69A4 100 65 270A9 375.61 487.93 1281.0 1 M S.6 1403.7 1459.4 1514 4 1569 4 1624.8 1680.7 1737.2 17943 003.08) e 0.1291 02932 0.4360 0 3655 0.6889 1.5090 1.5673 1.6154 1.6580 1.6970 1J335 1J679 12006 12318 1A617 e 0.0161 0.0!M 0.0174 0 0186 0.0204 0.6774 0.7828 0A759 0.9631 1.0470 1.1289 12093 12885 1.9669 1.4446 e80 6 70.11 16928 271.07 375.73 487 28 1271.1 1339.2 1399.1 1455.8 1511.4 1%6.9 16223 1678 9 1735.0 1792.9 (518.21) s 0.1290 0.2930 0.4358 0.% 52 0.6885 1.4869 1.5484 1.5960 1.6413 1.6807 1.7175 1J522 11851 1A164 1 A464 l e 0.0161 0.0166 0.0174 0.0186 0.0204 0.5869 0.6858 0.7713 0.8504 0.9262 0.9998 1.0720 1.1430 1.2131 1.2825 900 6 70.37 170.10 27126 375 84 487A3 1260.6 1332.7 1394.4 1452.2 15085 1564 4 1620 6 1677.1 1734.1 1791.6 (531.95) s 0.1290 0.2929 0.4357 0.% 49 0.6881 1.4659 15311 1.5822 1.6263 1.6M2 13033 1.7382 1J713 12028 12329 e 0.0161 0.01 % 0.0174 0 0186 0.0204 0.5137 06080 0.6875 0.7603 0 8295 0 8966 0.9622 1.0266 1.0901 1.1529 1000 6 70 63 17033 271.44 375.96 487J9 1249.3 1325 9 1389 6 1448 5 1504 4 1%1.9 1618 4 16753 1732.5 1790.3 (544.58) e 0.1289 0.2926 0 4355 0 5647 06876 1.M57 15149 1.% 77 1.6126 1.6530 1.6905 1J256 11589 1.7905 12207 e 0 0161 0.0166 0.0174 0 0185 0.0203 0 4531 0.5440 0.6188 0 6865 0 7505 0A121 0 2723 0.9313 0 9894 1.0468 1100 6 70 90 170.56 271.63 376 08 487J5 1237.3 13183 1384.7 1444.7 1502 4 1559 4 1616.3 1673.5 1731.0 1789.0 (%628) e 0.1289 02927 0 4353 0.5644 0.6872 1.4259 1.4996 1.5542 1.6000 1.6410 1.6787 1.7141 1.7475 1.7793 12097 e 0.0161 0.0166 00174 0.0185 0.0203 0 4016 0.4905 0.% 15 0 6250 0.6845 0 7418 0 7974 02519 0.9055 0.9584 1200 6 71.16 17018 271.82 37620 487.72 1224.2 1311.5 1379.7 1440.9 IM94 1556 9 1614.2 1671.6 1729 4 1787.6 067.19) s 01288 0.2926 0 4351 0.5642 0 6868 1.4061 1.4851 1.5415 1.5883 1.6298 1.6679 1J035 1.7371 1.7691 11996 e 0.0161 0.0166 0 0174 0.0185 0.0203 03176 0 4059 04712 0.5282 0.5809 0.6311 0.6798 0.7272 0 1737 02195 1400 6 71.68 17124 272.19 376 44 487.65 1194.1 1296.1 1369 3 1433 2 1493.2 15513 1609.9 1668.0 1726.3 1785.0 (587.07) s 0.1287 02923 0 4348 0. % 36 0.6859 1.3652 1.4575 1.5182 1.5670 1 6096 1.6484 1.6845 1.7185 1.7508 1.7815 e 0.0161 0 0166 0 0173 0.0185 0.0202 0 0236 0.3415 0 4032 0 4555 0.5031 0 5482 0.5915 0 6336 0 6748 0 7153 1600 6 7211 171.69 272.57 376 69 487.60 616 77 1279 4 1358 5 1425.2 1466 9 1546 6 1605.6 1664 3 1723.2 1782.3 M04E)s 01286 02921 0 4344

0. % 31 0.6851 0.8129 1.4312 1.4968 1.5478 1.5916 1.6312 1 6678 1.7022 1.7344 12657 e

0.0160 0.0165 0.0173 0 0185 O M 02 0.0235 0.2906 0.3500 0.3988 0 4426 0 4836 0.5229 0 5609 0 5980 0.6343 1800 6 7213 172.15 272.95 376 93 487.56 615 58 1261.1 1347.2 1417.1 1480.6 1541.1 1601.2 1660.7 17201 1779.7 M21.02) s 0.1284 02916 0.4341 0.% 26 0 6843 OA109 1.4054 1.4768 1.5302 1.5753 1.6156 1.6528 1.6876 1.7204 IJ516 e 0.0160 0 0165 0.0173 0.0184 0.0201 0.0233 02488 03072 0.3534 0.3942 0 4320 0.4680 0 5027 0.5365 0 % 95 2000 6 7326 172 60 273.32 377.19 487.53 614 48 1240 9 1353 4 1408 7 1447.1 1536 2 1596.9 1657.0 1717.0 1777.1 M3530) s 0 1283 02916 0 4337

0. % 21 O M34 0.8091 1.3794 1.4578 1.5138 1.5603 1.6014 1.6391 1.6743 13075 17389 e

0.0160 0 0165 0 0177 0 0184 0 0200 0 0230 0.1681 02293 02712 0.3068 0.3390 03692 03980 0 4259 0 4529 2800 6 74.57 173 74 274.27 377A2 487.50 612.08 11763 1303 4 1386 7 1457.5 1522.9 1585.9 1647A 1709.2 1770.4 ( M 8 11) e 01280 02910 0 4329 0.% 09 06815 0.8048 1.3076 1.4129 1.4766 15269 1.5703 1.6094 1.6456 1.6796 1.7116 e 0.0160 0.0165 0.0172 0.0183 0.0200 0.0228 0.0982 0.1759 0.2161 0.2484 0.2770 0.3033 0.3282 03522 0.3753 3000 6 75.88 17426 27522 378 47 487.52 610 08 1060 5 1267.0 1363.2 14402 1509 4 1574.8 1638 5 1701 4 1761 A M95 A3) s 0.1277 02904 0 4320 0.5597 0 67 % 0 3009 1.1966 1.3692 1.4429 1.4976 1.5434 1.5841 1.6214 1.6561 1.6886 0.0160 0.0165 0 0172 0.0183 0 0199 0.0227 O0335 0.1588 0.1987 0.2301 02576 02827 03065 0 3291 03510 3300 6 76 4 175 3 275 6 3787 487.5 6094 900.8 1250.9 1353 4 1433 1 15032 1570.3 1634A 1698.3 1761.2 (705 08) s 0.1276 02902 0 4317 0.5592 06786 01994 0.9708 1.3515 1.4300 1.4866 1.5335 15749 1.6126 1.6477 1.6806 e 0.0160 0D164 0 0172 0.0183 0 0199 0 0225 0.0307 0.1364 0 1764 0.2066 0 2 326 0.2 % 3 0.2784 02995 0.3198 i I 8600 6 77.2 1760 276.2 3791 487.6 608 4 779 4 1224 6 1336.2 14222 1495 5 1%33 16292 1693 6 1757.2 e 0 1274 0.2099 0 4312 0 5585 f)6777 01973 0.9508 1.3242 1.4112 1.4709 1.5194 1.M18 1.6002 14358 1.6691 q 0.0159 0.0164 0.0172 0.0182 0.0198 0.0223 0.0287 0.1052 0.1463 0 1752 0.1994 02210 01411 0.2601 02783 M 6 78.5 177.2 277.1 379A 487.7 606 9 763.0 1174.3 1311.6 1403 6 1481.3 1552.2 16192 1685 7 1750 6 s 01271 OJSR3 0 4304 0.5573 0.6760 CJ940 0.9343 1.2754 1.3807 1.4461 1.4976 15417 15812 1.6177 1.6516 e 0.0159 0.0164 0.0171 0.0181 0.0196 0.0219 0 0268 0.0591 0.1038 01312 0.1529 0.1718 0 1890 0 2050 0 2203 9000 6 81.1 1795 279.1 3812 488 1 604 6 746 0 1042 9 1252.9 1%4.6 1452.1 1529.1 1600 9 1670 0 1737.4 s 0 1265 0 2881 0 4287 0.5550 0.6726 0 1880 0 9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.5481 15863 1.6216 e 0.0159 0.0163 0.0170 0.0100 0 0195 0 0216 0.02 % 0.0397 0 0757 0 1020 0 1221 0 1391 0 1544 0 1684 0.1817 0800 6 83 7 1813 281.0 382.7 4886 602 9 736.1 9451 1188 8 13234 1422.3 1505 9 1582.0 1654.2 17242 e 0.1258 02870 04271 0 5528 0 M93 0 7826 0 9026 1.0176 1.2615 1.3574 1.4229 1.4748 1.5194 1.5593 1596.2 e 0.0158 0.0163 0 0170 0 0100 0 0193 0 0213 0.0248 0 0334 0 0573 0 0816 0.1004 0 1160 0 1298 0 1424 0.1%2 N 6 86.2 184 4 293 0 384 2 489 3 601J 729.3 901 8 1124 9 1261.7 1392.2 1482 6 1%31 1638 6 1711.1 a 0.1252 0J858 0 42 % 0 5507 0 6663 0.7777 02926 1.0350 1.2055 1.3171 13904 1.4466 1.4938 15355 1.5735 .g

L IBEBd9REoHGli ~ ~~ ~~ ? . ANSWERS -- PERRY 1&2 -87/06/02-BJORGEN, J. ANSWER 5.01 (1.00) As RPV water level is lowered, the driving head for natural circulation is decreased EO 5]. The resultant-reduction in core flow causes an increase in void fraction adding negative reactivity to the core C0.53. REFERENCE l PEI-B13, Attachment 45 Perry Thermal Sciences, pages 15-1 thru 15-5 l 293008K121 293008K134 295037K102 295037K209 295037K303 ...(MA'S) l ANSWER 5.02 (1.00) Limit is imposed to ensure net positive suction head requirements. (0.5) Possible consequence is cavitation and resulting pump noise and vibration and pitting and corrosion of pump parts. (0.5) REFERENCE PEI-E12 Perry Thermal Sciences, pages 17-20, 17-22 217000A105 217000A219 217000G010 217000K501 291004K106 295026K101 ...(KA'S) ANSWER 5.03 (2.50) 1. Decrease (0.5) 2. Smaller (0.5) 3. Higher (0.5) 4. M a rti mu m (0.5) 5. Below (0.5) REFERENCE Perry PEI-B13' Page 36; Perry SDM B21; NDPI, pages 10, 11 291002K107 291002K108- ...(KA'S)

---

.--_----------------,----.__---,,.__--_a

[ 1@$50$$$060lGEE p ANSWERS'--: PERRY"1A2; ' -87/06/02-PJORGEN,~.J. ,,o 1 ANSWER > '5 04 -( 2. 00 ), a. ' Fission 1 Product PoisonLBuildup. (0.5) lb.: Gadolinia.BurnupiE0.53'and Plutonium Buildup-[0.53. c.- FuelfBurnup. (0.5) ' REFERENCE-3-11, Perr'y Introduction to Nuclear. Reactor Operations, pages 2-61,'2-62, H ' 3 - 1 9,. 6 - 4,-. 6 - 5 292002K110 292007K103 ...(KA'S) 2 ANSWER-5 05 (2.00) a.. Less: Rod Withdrawal-(-0.5) -(due to Xenon decay) .b.: More. Rod Withdrawals (0.5). (due to heatup') c'- More Rod Withdrawal (0.5) (due to-heatup) d., No Significant Effect (0.5)- REFERENCE Perry Introduction-to Nuclear Reactor Operations, pages'6-11, 8 - 1' L292005K109 292006K114 292008K107 ...(KA'S) ANSWER 5.06 (1.00)

-Incr ease - [0. 53 due to less 2-phase flow resistance CO.53.

REFERENCE Perry Thermal Sciences, page 15-6 293003K123 293006H121 ...(KA'S) - ~ - - --._----____x_x _a

p IBE@GQQN6HGE; ' ~ ~ ~~ ~~~~ / ANSWERS'- P.ERRYLi&21 -87/06/02-DJORGEN,-Jo g. iANSWER 5.07-(1.00)

Saturation l pressure for 456; degrees?F is about 449 psia [0.53.

' 400,psig. converts to 415 psia CO.253. The'sause is^in error by'about 34 psi and is reading low E0.253. REFERENCE- .' Perry-Thermal-Sciences,Lpages 3-2. '293003K123 ... ( K A '.S ) : l? l ANSWER 5.08 (1.00)' L IncreasefCO.53.due to loss of-extraction steam'which causes a decrease in u feedwater temperature 100'.253. Due to moderator. temperature ' coefficient reactor power increases CO.253. REFERENCE Perry: Introduction to Nuclear Reactor Operations, page 6-11 Perry SDM:N36/25/26 L 292004K101-295005K202 29500SK205 295005K301 295005K303 ....(KA'S) ANSWER. 5.09 .(1.00)

a..

Longer 1'(0.5) b. Proportional (0.5) REFERENCE-Perry Thermal Sciences, page 10-8 Perry Introduction to Nuclear Reactor Operations, page 5-7 292008K101 293009K121 293009K127 ...(KA'S) i t a-d

[~510$$09Q20$0lGE ~ ~

ANSWERS

:-- PERRY. ' 1&2

-87/06/02-BJORGEN, J.- m , ANSWER. 5.'10 (1.00)

1C41-C001A 1C41-C0018-

. Standby Liquid Control-' Pump.

(Will.acceptf.any. of the~above)~

(1.0) REFERENCE Perry. Thermal-. Sciences,.page 17-6

Perry-Plant' Data Book, Tab Br.PDB-8002 291004K116:

-291004K119.. ...(KA'S) -ANSWER 5.11 (1'.00) a. (0.25) 'TheJ-higher control rod;-density will cause.more-voiding and-thus'a decrease-

in moderator.' density.

The moderator' temperature coefficient is s function of.the moderstor density...(0.'75) R'EFERENCE-Perry. Introduction.to Nuclear Reactor Oper ations, pages 6-11, 6-12' 292004K101 292005K105. ...(KA'S) ' ANSWER -5.12. (1.00) a.~. ' ( 1. 0 ) - REFERENCE' Perry Iritroduction.to.Nucelar-Reactor Operations, page 8-17 292006K107 ... ( K A ' S )' ANSWER' 5.13 (1.50) ,a. Decrease. (0.5)- -b. Increase (0.5) c.c Increase. (0,5) +

YO$50NDIObOlsI[ cANSWERS -- PERRYH182 -87/06/02-BJORGEM, J.~ REFERENCE fPerry Introduction to Nuclear. Reactor' Operations, page 6-20' Perry Thermal Sciences, page 2-30 292004K111 29200BK120 293002K104- ...(KA'S) ANSWER- ~5 14 .(1 5'0) a. ' Steam bubbles' generated'by' withdrawal of the, cod are carried upward-through'the remainder of the bundleLeausing increased void fract' ion and thus decreased power in the to'p of;the bundle [0.5]. Overall. bundle power may actually decrease. depending on the' relative magnitude: of the power increase in the bottom of the bundle and power decrease in the top of the bundle CO.5]. be Shallow tod. (0.5) ' REFERENCE LPerryLInt'roduction:to Nuclear. Reactor' Operations,'page~9-12' i 292005K112 ...(KA'S) - NSWER 5.15 .(2.00) i Decreases. ( 0. 5 '. The amount of subcooling is a function of.both ) recirculation flow and feedwater flow. In this case, recirculation flow' will increase more than feedwater flow-and thus subcoolins; decreases. -(0.5) The decrease in subcooling decreases the critical power. (0.5) Since critical Power is decreasins while actual bundle power is increasins ) the critical power ratio.will decrease. (0.5) REFERENCE ] ' Perry Thermal Sciences, page 10-7 293009K122 -...(MA'S) 1 ) l i i i -j l

y

IHEBdQQ2NeblG!!?

~ ~~ ~~~~~ '~ ((,' ANSWERS--rPERRYf1&2 -87/06/02-BJORGEN, J. H LANSWER' .5.16' '(3.00) L1 . Void, coefficient would add negative reactivity,first. 'The decrease

a.

-in_ pressure; caused by SRV opening would cause void production to increase.- b. 'Fuelltemperature' coefficient would add negative reactivity first. The rapid addition of positive _ reactivity due to rod removal causes a rapid-increase in power and fuel temperature. c".. Moderator temperature coefficient will adE positive reactivity first. The loss of feed heatins.will increase inlet subcooling. L (0.25 pts forLeach coefficient, 0.25 for + or - reactivity, 0.5'for'each reason) l l REFERENCE

Introduction to Nuclear Reactor Operations, pages 6-10.through 6-36 292004H101 292004K105 295014K203

....(KA'S) ANSWER 5.17 (1.50) l-CR1/CR0 = 1-K-eff 0/1-K.-eff 1 58/50 ='O.04/1-K-eff-1 K-eff-1 = 1.12/1.16 = 0.9655 (1.5) . REFERENCE Perry. Introduction to Nuclear Reactor' Operations, _page 5 ~292002K111 292002K112 292008K104 ...(KA'S) 7: l l i

ANSWERS -- PERRY 1&2 -87/06/02-BJORGEN, Jo ' ANSWER 6.01 (1.50) 'SDM R-10, Figures R10-9 (Rev. 3) and R10-10 (Rev. 3) 4 REFERENCE SDM R-10 262001K101 262001K103 ...(KA'S) ANSWER 6.02 .(3.00) a. 1. RHR shutdown cooling via CS1 suction. 2. Pool makeup using FPCC. 3. Pool makeup using condensate storage and transfer. 4. Condensate System. 5. Feedwater system. 6. HPCS. 7. LPCS. 8. LPCI (Any 5 e 0.3 pts each) b. 1. Suppression Pool Makeup. 2. Main Steam Lines. 3. RHR Siphon Paths. 4. Vessel Drain Paths. 5. RWCU Drain Paths. - l ) 6. Reactor Cavity Drain Paths. 7. Cask Pit Drain Paths. (Any 5 0 0.3 pts cach) REFERENCE ONI-G41 295023A202 ...(KA'S) i I i i 4

ANSWERS - --PERRY.1&2 -87/06/02-BJORGEN, J. 'iANSWER ' 6.03 -(- .50) Feedwat'erfLeakage Control System (0.5) REFERENCE. ' P e r r y.. S O I - E 2 1,- p a s e - 6.; 209001K103 -...(KA'S) LANSWER-6.'04 (2.00)' False. (0.5) (F010 will be closed any time.F031 is open.) a . Division 1 closes outboard ~ isolation _ valve F064. b.' ' False. (0.5) ( instead.) c.- True. (0.5) d. 'True. (0.5)' REFERENCE-Perry.SOI-E51, page:1a, Perry SDM E51,.page 34. 217000K107' 217000K201 217000K202 217000K401 ...(KA's) j ' ANSWER. ' 6.05. (1.00) a. c, e A. c a <pa.., a < w m 's ww ~ ary t ue s e4e k+ " ~ "N. 1K. (1.0) REFERENCE Perry SDM C34,.page 7 i 259001K109 '259002K104-259002K404 ...(KA'S) I ANSWER 6.06 (1.00) (1.0) c REFERENCE Perry SDM B21 NBPI ~216000K107 216000K307 218000K103 218000K201 218000K603 -...(KA'S) a .e

~ ANSWERS - EPERRY11&2 -87/06/02-BJORGEN, J.- a u ANSWER 6.07-(2.00.) a.. Level 8~(220") or.siishtly'above allowing forl valve stroke' time. -( 0. 5 % : L .b.- The IE22-F004' injection val,ve closes. (0.5) L 120/125). (0.5)' c.- IRM Flux Hi-Hi.( i J d. 1The. CST suction valve 1E22-F001 opens. (0.5) q REFERENCE System Description' Manual.E-22, Technical Specification 2.'2.1-209002A103 209002A301' 209002G010 209002K402- ...(KA'S)~ . ANSWER 6.08' (2.00) a. Increase (0.4), Increase'(0.4) b. . Lower (0.4)

c..

High (0.4), Decr' esse (0.4) REFERENCE .SDM B33, pg. 4 202001A109 202001A110 -202001A210 ...(KA'S) i ANSWER 6.09 (2.00) i a. Following initial. vessel depressurinati'on, the ECCS Systems restore level. .Because the jet pumps provide an enclosed floodeble volume. with the core arid shroud, water must either steam off out the top'of I the core or drain down through the bottom head area and up aridfout over the top of the jet pumps. The jet pump tapt coincide with 2/3 core height. (1.0) -l b. Due to the relative small jet pump no: le.and throat area, flow out the Jat pumps is restricted. Since vessel draindown must pass j through these no les, draindown is restricted. Total blowdown is, ) therefore, also restricted. (1.0) ] REFERENCE SDM B33, Figure 13 -202001K401 ...(KA'S) I l "I 1 i

-. _ - _ _ - _ = _ - ,n ANSWERSE-PERRY'i&2-E-87/ 06 / 02-B J O R G E N, : !J., ANSWER'

(.10-(1 00)'

If the ' n' a in. s te ain line were to break inside containment, which bypasses-i the suppressionffeature,'.the potential exists for a pipe rupture:to . produce significant-containment-pressures. (Alternate wording accep,ted.) l REFERENCE SDM.B21, pageL3' K 239001K117 239001K403 ...'(MA'.S). ANSWER 6.11 (1.50) p a. One light'for_each of three filter assemblies. (0.5) ( W i l l. a l's o ~ accept"high alarmr~ alert alarm, and rate alarni or 3-different alarm ~ points.) 'b. Improper! sample flow through the detector. (0.5) c. True. -(0.5); ' REFERENCE SDM D19'pages 15 and-16 272000A101-295034EA10 295034G006 ...(MA'S) . ANSWER 6 ~.12 : (1.75) a. 1. Moisture Separator Reheaters 2. Steam Jet Air Ejectors. 3.' Feedpump Turbines a 4. Steam-Seal Evaporators 5. Off-Gas Preheaters* -(Any-4'O 0.25 pts each) 'b. During Startups CO.25] and rapid load rejections E0.25].

35%.of total steam flow [0.253.

'LANSWERSL-. PERRY:1&2. -87/06/02-BJORGEN,1J. REFERENCEL ESDM B21,1pages 3 and.4 .i 239001K105L 239001K107. 239001K122 239001K407 -...(KA'.S) i ' ANSWER 16.13 (2.00) i a.: Drywell Temperature (.34) j Drywell Pressure. (.33) { Suppression Pool Temperature (.33) .i .l b.' No, E0.53 because the LCO is based'on a calculated arithmetic j -average of all the sensors-E0.5]. i ' REFERENCE j SDM'D23, pages 5, 6 and 8 a 223001A101 223001A109-223001G005 ...(KA'S) J l l f ANSWER 6.14- -(2.75) a.' 1. To remove heat-from the reactor and suppression hool under. normal and accident' conditions. (0.34) 2.- To automatically restore and maintain the desired water 11evel in the reactor following a LOCA. (0.33) 3.- To-control or reduce pressure in the reactor and containment after a LOCA. (0.33) ~ b. 125 psis. (0.25) -c.' 1. LPCI signal active for 10 minutes (0.5)- 2. High Drywell Pressure. (0.5) 3. High Containment Pressure (0.5) REFERENCE SDM E12 203000G004 -210000K101 226001K409 ...(KA'S) i j ~ u l l l i r-

• ~

l s i l j

' ANSWERS -- PERRY 182 -87/06/02-BJORGEN, J. < ANSWER 6.15 (1.00) The FCV opens up as reactor pressure increases, maintaining a constant flow and, therefore, constant Pressure, to the PCV. REFERENCE SDM C11, page 9 201001A101 201001K408 ...(KA'S) i ) a me

w v -QIQLQGIG6L CQHIBQL ~Be .ANSWERST- ' PERRY 182 -87/06/02-BJORGEN, Je 1 l ANSWER.

7. 0 1

/(3.50) 1 a. Firer.. toxic sas, high airborne activity, or any unfore.seen emergency f I ~which requires evacuation. (Any 3 0 0.5 pts each) ,LARM.and depress the manual scram pushbuttons. b.

1. -

2. Place the mode switch in SHUTDOWN. 3. Verify all. rods in-and power decreasing. [. 4. Trip the Main-Turbine i, 5.

Place the Division 3 D/G in local.

6. Transfer station loads to the startup transformers if-auto shift did:not occur. i --(Any.-5 G:0.4 pts each)- REFERENCE-ONI-C61 y 295016G007-295016G010 295016G011 ...(KA'S) l tj m mM sw i W

Bb$195991G$$_G922295 ~~~~~~~~~~~~~~~ ~ i ANSWERS -- PERRY la2 -877 06 / 02-B J O R G E N, J. 1 ANSWER 7.02 (2.00) (Any 4 0 0.5 pts each) .1. Knowing his current whole-body exposure. 2. Cooperating fully with health physics personnel in all matters pertaining to radiction protection. 3. Complying with procedures, instructions, and warnings signs or g barriers that concern radiation / contamination control. 1 I 4. Knowing the principal radiation sources and dose rates on the job q site. This information may be provided by Health Physics personnel j or from posted area surveys or radiation surveys attached to Radiation Work Permits (RWPs). 5. Properly using the exposure reduction tools and methods available. f 6. Discussing exposure reduction ideas with Health Physics and j supervisory personnel, and submitting ALARA Suggestions, if 1 appropriate, a REFERENCE PAP 0118, Paragraph 6.1.3 1 294001K104 ...(KA'S) J ANSWER 7.03 (1.50) 1. Automatic initiation is proven incorrect (by two independent indications). 3 2. Misoperation in automatic is confirmed. 3. Continued operation is no longer required. (3 e 0.5 pts each) REFERENCE PAP 0205, Paragraph 6.4 288000G001 ...(KA'S) e MM O

ggaeo - vauuowmuamoam-vm - mm~ ~ ~umum-mu- .BeQIDLQQIGeL GQtf1BQL

ANSWERS --LPERRY'282

-87/06/02-DJORGEN,fJ. ANSWER' 7.04 (3.50) a. Any14 of the followins 0 0'.5.each 1.- Personnel assigned are knowledgeable of.'the hazards-L { 2. Personne1' have proper safety equipment i

3..

Personnel are qualified for respiratory protection equipment' l The confined space is isolated and at atmospheric pressure 4. 5.. Personnel allowed to' enter are kept to a minimum 6.- Housekeeping and' material accountability are maintained 1 7 '. ' A confined; space entry permit.is prepared ji lb. Red (0.5) -Personnel. safety (0.5)- t ie. Plant Safety. Coordinator (0.5) REFERENCE PAPO516, Paragraphs 3.2, 3.6, 6.2.3, 6.1.2 l 394001K113 294001K114 ...(KA'S) l l q 1 3 F r

cB6DIQLQGIG86_GQNN QL: . ANSWERS-.-- PERRY-1&2 -87/06/02-BJORGEN, de .i t j ' ANSWER 7'.05 '(3.00)

a.

With no_CR0 pump running'(assumed)-for 20 minutes with.at 1 cast 2 CRD' 'l agegmulator. alarms of which~one'.is associated ~with a withdrawn rod t N* _e e u s o r, rose +c-

p. m e e,,v o ecr e::c, belcw 700 re4 s

0 ith two- -i a '(Alternate wording accepted) .mr~J-21:t;r alsra3 00,53. b.> PEI-B13, Reactor 1 Pressure Vessel!. Control,'-(will accept the-Emergency Procedure for. Reactor. Pressure Vessel Control) [0.53 1 because the entry conditions have,been-satisfied,Li.e., a scram c 4 a should have occurred 00.253 and reactor: power;is above 4% CO.253. c.

1. -

ARM and Depress'.the Manual Scram pushbuttors. l l

2..

. ARM and Depress the ARI pushbuttons.; 1 J' '3. Remove the'RPS fuses. 4.. . Reset the scram'and repeat., 5. Reset the ARI and repeat. 6. Individually scram rods 0 acci.imulators. 7.. Vent the scram air header. De e n -she CK s hy ;w% pow wy4b'"A C. 0M25[ptseahhW(a l # * *'M l'P#mY n'$ M b<O*O. .) (Any 4 REFERENCE- 'T/S~3.1.3.3, ONI-C11-1, PEI-B13, and S01-C11, Paragraph 7.6. 201001G011 295037G006 295037G008 295037G010 ....(KA'S) J .w- .e 9& 6 9

,c 15 ~Bhil0LQ9% COL _CQTISQL ~ l / -1 ANSWERS - J PERRYf1&2' -87/06/02-BJORGEN, J. g. ,s ' ANSWER: '7.06 .'(3.50) L s '. - -Recire' Loop A Flows Recire Loop-B Flows 'APRM; power' levels Total Jet. Pump 1 Flow-Jet: Pump. Loop (A) B total flow ( Ariy 3. 0 : 0.5 - pts each.) ~ Recirculate'an Flow Contro1' Malfunction. (0.5). b. Reactor , cl., '1.' Verify'Recirc. Loop Flow Balance 2.V Ent'er:0NILfo'r? Reactor:Recire Flow Malfunction 3./ Place'Recire Loop A' Flow' Control in. Manual and restore power. 4.. If' flow =cannot be controlled, ARM and Depress HPU A shutdown' i (Any 3 0 0;5-pts each) REFERENCE ONI-B-33-1, SDM B-33, ARI H-13 P680-4(q), ARI'H-13 P680-4 (37), ARI H-13 P680-4.(85) & (107) and ARI-H-13 P680-6 (49) 202002A108 202002A208 202002A209-4..(KA'S) ANSWER '7.07 (2.00) a. If the break is in a system other than Auxiliary Steam, cannot be ' isolated, and is severe encush' to require a Fast' Reactor Shutdown. (1.0) -- b'. 14 Close both recire flow control valves.until an APRM UPSC alarm is received or minimum position is reached. (0.5)- -) _0.5) 2.- . ARM and depress the manual scram pushbuttons. ( (Alternate wording' accepted) REFERENCE -ONI-Nil, Paragraph 3.3 '295006G010- ?95006C011 ...(KA'S) 1 1 i l

L TBsDIQL9GICsLiGQUI@QL ~ ~~ ~ l ANSWERS - -PERRY 182- -87/06/02-BJORGEN,'d.: 4 e l l I

ANSWER

7. 08 L

'(1.00) lq s ea. ' ( 110 ) : y REFERENCE l f*erry SOI-M14, page'1 223001G0101 ...(HA'S) l 1 L ANSWER' 7;09 (1.00) LIf f suppression pool' level :is below the top of the SRV discharge, opening-the' ADS valves 1will cause-direct pressuri:stion of th'e suppression pool which may' exceed.the capability of the containment. (1.0) REFERENCE-PEI-B13, Attachment 1 .G.~E..Emersency Operating Procedure Fundamentals,.page=C2-1. 218000K302 295025A204 295030K208 295030K301 ...(KA'S) -) ANSWER 7.10 (2 00) l E. Atfuel rack lockout exists upon diesel shutdownhhichcauses it to be i. unavailable for a LOOP or.manuel start.for 2:to 3' minutes.) (1.0) e r b.,4 % L e sd s m u b e. e ra ble /~ u 5 6,4 pv..48:. 4.im, 'b. To prevent senerator reverse power condition. (1.0) . REFERENCE S01-R43, p a's e - 2 264000A201 264000A202 264000G010 ...(KA'G) .] i i e l I l .m o '*NW'k 99

' 6.e.__tuu6tuvuni:_nunceLi_eunutae61_stimuktu6Leuw. m k Jaz 4 . 890IQLQGIC6L_GQtf1BQL YANSWERS5-. PERRY 182 -87/06/02-BJORGEN,L de s ' ANSWER?

7. '.11 :

'( 3. 5 0 ) - e a. ToJavoid rapid injection of' cold unborated water;during-Ldepressuri::stion and thus ' the resulting '. reactivity. excursion [0.53. Bot.on injection.and.CROH flow ate continued to achieve reactor: shutdown'[0.53.. ~ "b.. -Kept:above MARFP.to provice. sufficient steam flow through the open SRV'.s to-ensure-adequate steam cooling:to an uncovered core..EO.b]. Kept'as--low as practicable.to control.the flooding rate and.thus .'possible power' excursions.. (0.5) c. Would' indicate that water is. entering the RPV at'a rate'less than .the rate'of steam production and therefore,-RPV. water.' level-is decreasing. 0.5) ( Ld.- . Motor-driven. pumps are necessary 'because the RPV: will. be ~ depressurimed. Prior..to flooding [0. 53.. Systems injecting outside-e the shroud.are preferred to minimize cold water reactivity addition.00453. REFERENCE P E. I-B 13, A t't a c h m e n t'- 4, G.E. Emergency Operating Procedure Fundamentals, l pages_C6-1'through C6-3. 216000K324-295031G012 295031K304 295037G012: ....(KA'S)' l ) e i ---,----,------.-.--___.----,-_------_~--,,,----J

ANSWERS -- PERRY 1&2 -87/06/02-BJORGEN, J. I k i ANSWER 8.01 (2.50) a. No, E0.53, the Remote Shutdown Panel is not ' capable' of performing l its required function E0.53. l b. Declare both Divisions of the Remote Shutdown Panel inoperable [0.53 and comply with the action statement of Tech Specs E0.5]. c. The plant must now be placed in hot shutdown within 12 hours E0.5]. REFERENCE l Technical Specification 3.3.7.4, and the Definition of Operable, Definition 1.29 295016G003 ...(KA'S) ANSWER 8.02 (3.00) a. By completing Attachment 2 to PAP-0110 [0.53 and obtaining the appropriate level of management approval E0.5]. (Alternate i wording acceptable) b. No, [0.5]. The shift position cannot be left unmanned due to an oncoming member being late [0.53. i c. The Shift Supervisor could be declared ' incapacitated' due to fatigue E0.253. He is maintaining the capability of communication with the Control Room [0.25], and the arrangement should be authorized by an appropriate level of P ant management E0.25], and l the Shift Supervisor can relieve the Uriit Supervisor E0.25]. A proper turnover is performed for each relief E0.25]. (Any 4 0 0.25 each) 2 REFERENCE PAP-0110, " Shift Staffing', Paragraphs 6.1.2, 6.1.3, 6.3.4, 6.3.5, 6.4.1, 6.4.2, 6.4.3. 294001A109 ...(KA'S) l I 1 I l l ____u

vacaavavavucaaavavaaavavuvauvaauvavucuuauaccoucuvavamvvowu ~- . ANSWERS -- PERRY 1&2 -87/06/02-BJORGEN, J. l ANSWER '8.03 (1.50) a. To request a Safety Evaluation. (0.5) l b. Contamination concentration below 10 CFR 20 limits [0.5] or all potential leak paths are identified and potential releases are prevented [0.5]. (Alternate wording accepted) t REFERENCE l PAP-0201, Paragraph 6.7.6.4 204000G010 ...(KA'S) i ANSWER 8.04 (1.50) t Yes, [0.53, limits are 92 x 1.25 = 115 days [0.25] per quarter, not to exceed 92 :: 3.25 = 299 days total [0.253. Maximum quarterly period was 104 days [0.25] with a total of 293 days E0.25]. 4 i Aug Sept Oct Nov Nov Dec ] 1 21 30 31 10 (92) 20 31 l l Jan Feb Feb Mar Apr May 1 31 15 (97) 13 31 30 30 (104) Total: 293 REFERENCE Technical Specifications 4.0.2 209002G006 ...(KA'S) l l I 6 l e -w -mme o

J ~ A N S W E R S ~ -- P E R R Y- -- 18 2 - -87/06/02-BJORGEN, Jo i T ANSWER 8.05-(2.00) l a.- Turn.the. handwheel.in the closed direction 1/4-1/2 turne then' reopen the' valve. -(0.5) - j l b.- '1'. The part changeout constitutes a design' change or, j modification. '. J d 2. The substitution may affect operability or' reliability and j should, therefore,' receive a formal engineering' review. i i f 3.- 'The valve is' safety related, so a-formal Work Order should.be used. J l 4. . The-part'changeout, as a minimum, is corrective maintenance and j requires a Work Order. 1 5.. Other valves have apparently been done and may be' inoperable. 1 ~ l -(Any three 9 0.5 pts.each Alternate wording accepted) I REFERENCE PAP-0205, Paragraph 6.6.2.; PAP 0902,' Paragraphs 2.3 and 2.4; and PAP 0905,- ~ Paragraph 2.2 .209001G006 209001G010 209001G011 ...(KA'S) a ( j) i %e ' ANSWER = 8.06 (2.50) a. Results in a loss of secondary containment integrity (will also accept loss of secondary containment vacuum and failure to keep the containment access door (s) closed except for routine entry and exit) i CO.53 during activities with a potential for draining'the reactor vessel [0.53. .i l b.- The annulus differential pressure ' low" alarm. (0.5) l .c. Suspend core alterations / operations with a potential for draining the reactor vessel. (0.5)- I G - ; ~.6S e e u rit y S h i f t S @2r+iwA + n nbtain_wrlitren+ r m 65' Ion 1 ^ Tro D ow C vi s ti-cl Room finit 9n a ~ sor _rior tn o n tting v y eziT T5 y I 4eeondury access por W (0 3 Cg M p REFERENCE l LER 86-076, Rev. 01 '290001G010 290001G011 ...(KA'S) J 1 i! 7-. l -I - - - - - - - -. - ~ -, - - - - -- - - -. - - - - - ---x-

-,((: ANSWERS'---PERRY.Ja&2 -87/06/02-BJORGEN, "J. : c'(l. !: ANSWER-8.07 -(1'.50)~ ' At -least two independent 's'amples are collected and analy::cd.. (0.5) l ~ h 11 : 2.- 'At'least:two. qualified persons.:must-independently verify the release -l r ate' calculations.'EO.5] and discharge line valve lineup [0. 5]. - ' ( 1. 0 ) ' j l b REFERENCE'. [ Technical' Specifications 3.3.7.9,. Action-110'.and LER 87-11. l..

272000G010;

...(KA'S)' 1 l-l- 1 -l s' .: ANSWER. 8.08.. (2.00) J a.- 1. ECCS. initiation.and. injection j 2. ReactorLProtection System Actuation l 1 3. Declaration of Emersenc._ Class-i 4 ESF Ac4 M i+w (2 of the'~2' required --0.5 pts each) d' gsF 49 di 1 y

b..

Reactor Protection System Actuation or (if carrdidates remember the. event) RCIC equipment failure of inboard steam-isolation valve.. (0.5)- i 'c. All ECCS injections must be reported. (0,5) REFERENCE LER 87-012, '10'.CFR 50.72, 10 CFR 50.73, Technical Specifications 3.~5.1, Action-s. .2950310002. 2950310007 ...(KA'S) ANSWER 8.09 -(1.00) (: 4 c. (1.0) REFERENCE I Technical Specifications 3.3.1 and 3.3.2 i 272000G005 272000G010 ...(KA'S) -l 1 i ee-g- M-4 S'P _ _ _ _ _ _ __=-_ ____ _ _______:- _ ________ _________________ _ _______ _ _ ___ _ _ _ ___ _ _

ANSWERS - -PERRY 182 -87/06/02-BJORGEN, J. ANSWER 8.10 (2.00) i a. The Unit Supervisor [0.5],~then the most senior On-shift Supervising Operator.CO.5]. b. Inform plant management, GSO or above CO.53, and initiate action to obtain replacement personnel E0.5]. (Alternate wording accepted) i i REFERENCE l PAP 0110, Paragraph 6.1 3 I {l 294001A109 294001A111 ...(KA'S) J ANSWER 8.11 (3.00) l i J a. False (0.5) l b. False (0.5) c. False (0.5) d. True (0.5) i e. False. (0.5) { f. False (0.5) ) l REFERENCE PAP 0110, ' Shift Staffins' and Technical Specification 6.2.2 294001A103 ...(KA'S) I l' J 1 ANSWER 8.12 (1.50) a. True (0.5) b. False (0.5) { c. False (0.5) REFERENCE PAP 0D22, ' Temporary Changes to Instructions'. 294001K116 ...(KA'S) l

ANSWERS -- PERRY 182 -87/06/02-BJORGEN, Jo ANSWER 8.13 (1.50) A Type A is the integrated leak rate of primary containment performed during a major outage or the entire containment is tested 0 11.3 psis for several hours (every 40 + 10 months). (0.5) j, Type B is a local leak rate test of gasketed joints and electrical penetrations or drywell airlock test or elect penet E318 (other examples accepted) (0.5) Type C is a local leak rate test of valves in piping systems,'such as I testing the MSIV's for leakage. (0.5) (Other examples accepted) REFERENCE Technical Specifications 3.6.1.2, 4.6.1.2, 10I-1, PAP 1114 223001G006 223001G010 223001K101 ...(KA'S) t I \\ -l' i 1 I T

t-VALUE- *,. REFERENCE '.00ESTlVN -

\\

s. e t 03.01 1.00' HED0000206 03.02 1.00 HED0000207 e CL O3 2.50 HED00Clp208 6 05IO4 2.00 HED0000209 g" 05.05 2.00 HE00000210 q 05.06' 1.00 HE00000211 i 05.07 1.00 H E D 0000?,12 05.00' 1.00 HED0006213 4 _0,5.09 1.00 HED0000214 05.10 1.00 HED0000215 05.11 1.00 HED0000216 i 05'.12 1.00 HED0000217 h,LCDQ000218 '05 13 1.50 ' s ey.14. 1.50 HEL9000219 '(Ob.05 2.00 'PrD0000220 05.16 3.0' ,.HEPdOOO221 + \\ 05.17 1.50 if f,EL' 000222 0 ....5. 25.00 4 06'.01 1.50 HED0000223x 06.02 3.00 HED0000224 06.03 .50 HED0000225 4 6 I)1 O' (OS 2.00 HED0000226 'u '\\

06. 5x 1.00 HED0000227 s

06. 8 1.00 HED0000228 1

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TEST CRDSS REFERENCE PAGE 2 f= { GUESTION 'VALUE REFERENCE l 1 79 08.02 3.00 HED0000250 08.03 1.50-HED0000251 08.04-1.50 HED0000252 l 08.05 2.00. HED0000253 08.06 '2 50 HED0000254 l 06.07 'i.50 HED0000255 j .08.00 2.00 HED0000256 1 00.07 1 00 HED0000257 08.10 2.00 HED0000258 08.'11-3.00 HED0000259 08.12 1.50 HED0000260 08.13' 1.50 HED0000261 25.50 102.00 4 .,) t i

j

^

1 l U.. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: PERRY 1&2 REACTOR TYPE: BWR-GE6 . Q DATE ADMINISTERED:._87/06/01 3 1 . s.4, EXAMINER: DANIELS. M. CANDIDATE: I 'INEIBUGIl0HE_IQ_CANDIDAIEL Uso separate paper for the answers. Write answers on one. side only. Steple question sheet on top of the answer sheets. Points for each .quastion are indicated in parentheses after the question. The passing grcde requires at least 70% in each category and a final grade of at j least 80%. Examination papers will be picked up six (6) hours after i tho examination starts. i % OF ' CATEGORY.% OF CANDIDATE'S CATEGORY VALUE TOTAL SCQBE.. _ VALUE CAIEQQRY Jr. 0 0 i _25.00 ES-Ot 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW gy 44-40 25.00 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 7206 _2E QQ__ 25-02 3. INSTRUMENTS AND CONTROLS i 7 F. e 4 25.00 25.00 _ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 'l 9. 7)~ 400.00 Totals Final Grade .All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature 1 i l

~ NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 'During'the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties. 2. Restroom trips are to be limited'and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. 3. Use black ink or dark pencil En1r to facilitate legible reproductions. 4 '. Print your name in the blank provided on the cover sheet of the examination. '5. Fill in the date on the cover sheet of the examination (if necessary). 6c Use only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of gash section of the answer sheet. ) 8. Consecutively numb'er each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write onlY en Ent Eide of the paper, and write "Last Page" on the last answer sheet. ) ' 9. Number each answer as to category and number, for example, 1.4, 6.3. '10. Skip at least thras lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use. abbreviations only if they are commonly.used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as~a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the naaminar only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed.

18. Whan.you completa your oxcmination, you shell:

a. Assemble your examination as follows: '(1) Exam' questions on top. l (:2 ) Exam aids - figures, tables, etc. (3) Answer.pages. including figures which are part of the answer. b. Turn in your copy df the examination and all pages used to answer the examination questions, c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions, d.. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked, i f .__-.____-____-___-_.-_--__.D

[ ' ~ THsidlQD1H&tilCS HEAT TRAHEFER AND_ELUID FLQH' l L I QUESTION 1.01 (1.50) Saturated steam is admitted to an ideal turbine at 750 psia and exhausted to a condenser at 3 in Hg. Datermine the following;

a. The outlet enthalpy (h2)

b. The-steam quality at the turbine outlet (x2)

c. The turbine work output (W/J) out QUESTION 1.02 (1.50)

DEFINE the following methods of heat transfer;

a. Conduction

b. Convection

c. Radiation

. QUESTION 1.03 (1.00) The temperature of feedwater leaving a feedwater heater is 320 F. CALCULATE the MINIMUM PRESSURE required for the extraction steam I cupplying the feedwater heater? (Assume 100% heat transfer) QUESTION 1.04 (.50) Answer the following TRUE or FALSE 1 ' Nucleate boiling may occur in a liquid when the bulk liquid j 't:mperature is highly subcooled. I 1 I 1 1 l 1 (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) i )

- 7 1HERMODYNXMICS. HEAT TRANSFER AND FLUID FLOW 1 QUESTION 1.05 (1.00)_ CHOOSE Which of the following statements is true concerning a BWR core 7

a. The Maximum Linear Heat Generation Rate (MLHGR) is the Linear Heat Generation Rate (LHGR) multiplied by the total surface area of the active fuel rods.

b. The Linear Heat Generation Rate (LHGR) is the reactor power in KW divided by the total surface area of the active fuel.

c. Power density is reactor power in KW divided by the Linear Heat Generation Rate (LHGR).

d. The Maximum Linear Heat Generation Rate (MLHGR) is the reactor power in KW divided by the total active length of the fuel

.j pins in the core, times the total peaking factor, j i 1 QUESTION 1.06 (1.00) Consider two (2) nearly identical centrifugal pumps operating in l parallel. Which of the following statements MOST CORRECTLY DESCRIBES l l the operating characteristics of the pumps?

a. The total brake horsepower for the two (2) pumps is one half i

the horsepower for a single pump.

b. The total head for the two (2) pumps is the sum of the individual pump heads for a given total capacity, I

c. The total flow for the two (2) pumps is twice the flow for a single pump.

d. The total brake horsepower for the two (2) pumps is less than twice the horsepower for a single pump.

l l QUESTION 1.07 (1.50) I a. DEFINE the ter.n CONDENSATE DEPRESSION. (0.50)

b. STATE Why condensate depression in excess of 8 to 10 F is an undesirable operating condition.

(1.00) l (***** CATEGORY 131 CONTINUED ON NEXT PAGE *****) l l l

QUESTION 1 08 (1.50) A core thermal power heat balance is used to determine core thermal

power. LIST and-EXPLAIN two (2) of three (3) alternate methods which can be used to ESTIMATE core thermal power.

QUESTION 1.09 (1.00) CHOOSE which of the following statements is TRUE concerning heat added to subcooled water. ~

a. Water enthalpy will increase, but entropy will decrease.

b. Both entropy and enthalpy will increase.

l l

c. Entropy will increase, but enthalpy will decrease.

d. Enthalpy will increase, but entropy will remain essentially the same, j

l b i i 1 (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) o

IEEMODYNAMICS. HEAT TRANSFER AND'FLUIf FLQN j 4 QUESTION 1.10 (2.00) The Perry Unit 1 core has been unloaded for in vessel work and is boing reloaded with new fuel.. Sources have been installed prior to the-fuel loading. The INITIAL count rate was 30 counts prior to' loading fuel.The following changes in count rate are recorded on the 'Sidi channel during the fuel load sequence; Bundles loaded count rate 50 32 100 33 150 37 200 55 250 100 Using Figure 1 answer the following; a.- PREDICT the number of fuel bundles required to be loaded in order to achieve criticality.

b. STATE the conclusion that can be derived from the count rates as to the placement of the sources in relation to the

detector, c.

The number of fuel bundles calculated for criticality after loading 150 bundles, would be (CONSERVATIVE, NON-CONSERVATIVE). EXPLAIN your reasoning. QUESTION 1.11 (1.50) a. STATE why Gadolinium is loaded into the Perry Unit 1 core.

b. STATE if the axial distribution of Gadolinium in the core, is (EVENLY DISTRIBUTED, DISTRIBUTED TOWARDS THE TOP or DISTRIBUTED TOWARDS THE BOTTOM)

c. EXPLAIN why the Gadolinium is distributed in this manner.

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

1; PRINCIELES OF NUCLEAB POWEB_ PLANI OPERATION. -PAGE, 6 IHERM0 DYNAMICS. HEAI_IBAHSEER AND FLUID FLOW QUESTION 1.12 (2.00) A hot reactor startup is in progress,.at BOL, with.a Keff of.99.A RAPID C00LDOWN OCCURS reducing the temperature by 110 F.

a. CALCULATE the total reactivity change due to the temperature.

l change.

b. CALCULATE the resultant Keff after the temperature change.

i

c. CALCULATE the resultant reactor period due to the temperature change.

d. STATE and EXPLAIN what will terminate the power increase?

(0.50 ea) QUESTION 1.13 (2.50) For each'of the following events, STATE WHICH coefficient of 1 reactivity would act FIRST to change reactivity and whether POSITIVE or NEGATIVE reactivity is added due to that coefficient.

a. Control rod drop at power.

b. SRV opening at power, c.

Loss of shutdown cooling when in shutdown.

d. Main turbine trips while at 30% power.

e. Loss of one feedwater heater (loss of extraction steam)

I QUESTION 1.14 (2.00) The reactor has scrammed from 100 hours operation at full power. Ten (10) hours later a cooldown is complete and the reactor is determined to be shutdown by 1% dk/k. DESCRIBE the changes which occur, if any, to the reactivity by which the reactor is shutdown over the next twenty (20) hours. INCLUDE in your description any adverse conditions which may occur as a result of the cooldown. (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

k h

1.

PRIHQ1ELESLOF NUQLEAE_EQHEB PLAHI_ OPERATION,- PAGE 7-THEEMODYHAtiICS. HEAT TRANEEEE AND FLUIQ_ELQH L i QUESTION: - 1.15 : ( 1. bO ) - CHOOSE which of the following conditions has the most significant thermodynamic effect.

a. A spurious HPCS injection at 15% power.

b. A spurious HPCS injection at 85% power.

l' l EXPLAIN your choice l l QUESTION 1.16 (3.00) l-A reactor startup is in progress. A critical rod position has been ' calculated for the existing conditions. Rod pulls are~ started for the approach to criticality. STATE How each of the following conditions, i I or events, affect the CRITICAL ROD POSITION (MORE ROD WITHDRAWAL, LESS ROD WITHDRAWAL, NO SIGNIFICANT EFFECT). 1

a. One Reactor Recire Pump is stopped

b. XenonHis changing-due to extended power operation terminated L

sixteen (16) hours previously. i c. Shutdown cooling-is terminated,

d. The reactor head vent is inadvertently closed,

e. Moderator temperature is gradually decreasing.

f. RWCU isolates.

i (***** END OF CATEGORY 01 *****)

2. PLANT QEElGN INCLUDING SAEETY AND' EMERGENCY SYSTEMS PAGE-8 l . QUESTION 2.01 (1.50) i There are five (5). amber windows for each ADS channel, indicating a variety i of ADS malfunctions. LIST three (3) of the five (5) malfunctions. QUESTION 2.02 (1.50) j l Concerning the Main Steam Line Radiation Monitoring system; l l Main Steam Line Radiation Monitor channel "B" has been declared INOP, and is in a TRIPPED condition. A high high alarm is received on channel "A" STATE what ACTION / ACTIONS is/are initiated by this condition I QUESTION 2.03 (1.50) Standby Liquid Control storage tank outlet valve F001A (F001B) is closed 1 during normal operation. LIST three (3) ACTIONS or CONDITIONS which will open the valve. j I QUESTIOh 2.04 (1.75) lei'O l Concerning the RHR system in the Containment Spray mode; l '1 STATE the signals that will automatically initiate Containment Spray. (INCLUDE SETPOINTS) l QUESTION 2.05 (2.50) Concerning the Low Pressure Core Spray system (LPCS); I

a. STATE the automatic initiation signals.(INCLUDE SETPOINTS)

b. LIST four (4) of the six (6) OPERATING PARAMETERS, (COMPONENT POSITION INDICATIONS) which must be verified when the system initiates in the Emergency Mode of operation.

l

c. Are these verifications required if the LPCS system is initiated manually?

1 1 1 l (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****) l )

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 t QUESTION ^ 2.06-(1.50) Concerning the RCIC system; a.The RCIC turbine trips due to the activation of the turbine trip logic circuit. STATE how the turbine trip can be reset

b. STATE how the mechanical overspeed can be reset.

c. STATE what effect reactor water level will have on the RCIC turbine after automatic initiation.

QUESTION 2.07 (1.00) 'Concerning the reactor core; 1 STATE and EXPLAIN the design feature of the individual' fuel rods that provides protection against fuel cladding failure due'to hydriding. \\ . QUESTION 2.08 (2.00) A-rupture of the reactor coolant boundary in the drywell, causes drywell pressure-to increase. WHAT DESIGN FEATURE of the drywell provides for the reduction of this pressure? Include in your discussion the SEQUENCE OF EVENTS as PRESSURE INCREASES. QUESTION 2.09 (4.00) tyf The Safety Relief Valves (SRV's) at Perry are designed to operate in ( different modes. g

a. LIST the four (4) modes of operation.

Lb. DESCRIBE how each mode is initiated. c.WHAT PROTECTION is provided for each mode of operation. (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2.

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 'PAGE 10, l k a

QUESTION 2.10 (2.00)

There are'two (2) levels of undervoltage protection for loss of off-site power for'the Division I andLII class 1E buses.

a. LIST the two (2) levels of protection. (INCLUDE SETPOINTS)

)

b. STATE actions and alarms initiated by the two (2) levels of i

protection. (ASSUME NO LOCA SIGNAL PRESENT) LIST ONLY THOSE ALARMS-AND ACTIONS WHICH ARE A DIRECT RESULT OF THE i UNDERVOLTAGE . QUESTION 2.11 (1.50) Concerning the End of Core (EOC) Life Interlock for the Recirculation system;

a. STATE the conditions which will initiate EOC action.

b. STATE effect-on the recirculation system,

c. Why is this action required?

i QUESTION 2.12 (1.00) Concerning the vessel and recirc system thermal shock protection;

a. STATE the CONDITION / CONDITIONS that will' result in the protection being initiated,

b. STATE the ACTION / ACTIONS or RESULT /RESULTS initiated by the protection circuit activation

-QUESTION 2.13 (1.75) Concerning the Standby Diesel Generator; STATE the permissives which are required to be met in order to CLOSE the Diesel Generator OUTPUT BREAKER from the control room. l (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN 7NCLUD2HG SAFETY AND EMERGENCY SYSTEMS PAGE 11 QUESTIONJ 2.14 (1.50) Concerning the High Pressure Core Spray System (HPCS);

a. STATE the design feature / features of the HPCS suction strainer that assures / assure adaquate NPSH to the pump.

b. The HPCS suction strainer is located deep in the suppression pool. STATE two(2) reasons why it is located in this position.

l 1 l l 1 l l I 1 l (***** END OF CATEGORY 02 *****)

f 3-. INSTRUMENTS AND CONTRQLS. PAGE 12 QUESTION 3.01 (1.50) The Reactor Feed Pump Turbines are prevented from starting by low condenser vacuum 11.5. INCHES Hg absolute

a. STATE how a Reactor Feed Pump may be started if condenser low vacuum exists.

b. STATE how-the operator can determine that a Reactor Feed Pump can be' started with an existing low vacuum condition.

c. LIST what condition / conditions will automatically place the low vacuum function back in service if the Reactor Feed Pump has been started under low vacuum conditions. QUESTION 3.02 (2.50) The main turbine generator is protected by a runback circuit which is initiated'by a loss'of coolant to the generator, a. LIST two (2) INITIATING SIGNALS,(INCLUDING SETPOINTS), which will cause a. turbine runback (1.00) l

b. STATE the time required for.the turbine to run back to the "no liquid coolant value"? (assume the turbine is at rated load when the-runback occurs)

(0.25) c. STATE what generator protection is provided if the runback HAS NOT automatically-reduced turbine load. (INCLUDE TIMES AND SETPOINTS IF APPLICABLE. (ASSUME THE INITIATING SIGNAL / SIGNALS STILL PRESENT): i i (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) 1 i J

3.

INSTRUMENTS AND CONTROLS PAGE 13 l l j QUESTION 3.03 (2.00) j i Icolation valves for the Instrument Air System close to isolate Instrument i Air from the Containment and Drywell. For the valves listed in column 1, 1 MATCH the proper isolation signal from column 2 (Isolation signals in column 2 may be used more than once) l COLUMN 1 COLUMN 2

a. Valve F200 Containment /Nv/,r

1. Drywell pressure 2 psig Isolation

b. Valve F160 Containment h v /sc#2. Reactor Water Level Level II

/ Isolation Valve F170 ContainmentpY dC/i3. Drywell Pressure 1.68 psig c. Isolation

d. Valve F646'Drywell

4. Reactor Water Level Level III Isolation

5. Reactor Water Level Level I l

QUESTION 3.04 (1.50) LIST THREE (3) prerequisites which must be met before the IRM detectors can l bo withdrawn from the core. l QUESTION 3.05 (1.00) i From the following statements, SELECT the one which MOST ACCURATELY I DESCRIBES an LPRM detector. a. The detector is a fission chamber pressurized to ~3 atmospheres with Argon gas and coated with U 235. 1

b. The detector is a compensated ion chamber pressurized to ~3 atmospheres with Argon gas and coated with a variety of Uranium Isotopes.

c. The detector is a fission chamber pressurized to ~ 5.6 atmospheres with Argon gas and coated with U 234.

d. The detector is a fission chamber pressurized to ~ 1.2 atmospheres with Argon gas and coated with a variety of Uranium isotopes.

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

. 3 =. INSTRUMENTS AND CO'NTROLS PAGE 14 ~ 1 QUESTION 3.06-(1.25) LFill in the blanks with the correct wording; .A HIGH-RADIATION alarm received from-any readout module from radiation monitors'K650 (Common Refueling Operation Atmosphere) K660 (Containment Vassel and Drywell Purge Exhaust) and K680 (Containment Atmosphere) will Gnergize the __(a) alarm. This alarm sounds horns in the __(b)___ the -(c) and the (d) In addition it energizes (e) outside the containment upper and lower personnel air locks and the l Gquipment hatch. (THE. BLANKS MAY REQUIRE MORE THAN ONE WORD) -QUESTION 3.07-(1.00)- If.the temperature of'the water in the reference leg of a high temperature .high pressure tank level instrument were to DECREASE, the indicated level would a (INCREASE, DECREASE). If a leak developed in the same reference-leg, the indicated. level would b (INCREASE, DECREASE) l ' QUESTION -3.08 (1.50) Located on panel P680 are two (2) pushbuttons labeled " Volume Test -Channel A and Volume Test Channel B". -a. STATE the actions / action which take/ takes place if one of the pushbuttons is depressed (0.50)

b. STATE the actions / action which take/ takes place if both of the i

buttons are depressed (0.50) eff. What INFORMATION is available to the operator to determine the actions have taken place? (0.50) I i 1 l 1 (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) 1

.3; INSIBMMENTS AND CONIBQJe PAGE 15 QUESTION 3.09 (2.00) l Concerning the Emergency Diesel Generators; SELECT from column 2 the proper words to make the statements in column 1 correct. COLUMN 1 COLUMN 2 i

a. Going in.the increase direction on the

1. Increase Frequency voltage regulator, while running

2. Decrease voltage on an isolated bus will

3. Decrease frequencyL l

4. Change KVAR load

b. Going in the increase direction with

5. Change. voltage the governor while in parallel with

6. Decrease KW the grid will

7. Increase voltage

8. Increase KW

[

c. Going in the lower direction with the voltage regulator while in parallel with the grid will

d. Going in the raise direction on the governor with the generator on an j

isolated bus will j QUESTION 3.10 (.50) One of the Off Gas Post Treatment Process Radiation Monitors (DM-K601A or DM-K601B) senses radiation in EXCESS of its high-high alarm l cctpoint. STATE what automatic actions / action take/ takes place. ) l l l \\ l l \\ i (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

J/?: a 1 1 + (',: ~ 3; INSTRUMENTS AND CQNTROLS -PAGE 116' i QUESTION 3.11 (1.00)- Concerning!the Remote. Shutdown System-1 ' SELECT from the following the statement which MOST ACCURATELY { .describesLthe. control. functions. 4

a. With ths Remote Shutdown-Transfer Switches (RSTS) in the EMERGENCY" positioni valve position information is displayed in

.the control room and the Remote Reactor Shutdown Panel-i

b. All. automatic control functions for the valves on the Motor Control-Centers (HCC) are removed when the RSTS is placed in'the

" EMERGENCY" position

c. The RSTS switches transfer control and normal power suppli'es.to the

Remote Shutdown Panel

d. All Remote Shutdown Control Switches (RSCS) must:be'left in the l

'! SPRING RETURN" position unless the Remote. Shutdown Transfer Switch (RSTS)'is in the " EMERGENCY" position QUESTION 3.12. (1.00) Concerning the Reactor Protection System; 1 CHOOSE from the.following which combination of Manual Scram Pushbuttons will Lnitiate a reactor scram. (EXPLAIN YOU CHOICE) a."A" and "C" Lb."A" and "D" c."B" and "D" QUESTION. 3.13 (1.50) Concerning the Control Room Operated Area Radiation Monitoring System; STATE AND EXPLAIN-the.effect on the(LOCAL and REMOTE) Alarm and Indicating' units ~if.the power supply to the Control Room Readout Module were' lost. .(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

l l l 'l&__ INSTRUMENTS AND COEIBQLE-PAGE 17' L ^ l l L! '~ QUESTION 3.14 (1.50) 1 L (3) functions (purposes) of the main steam line flow I LIST three rostricters. ] i l l QUESTION 3.15 (2.00) Concerning the Redundant Reactivity Control System; a. LIST the initiating signals for the Alternate Rod Insertion System (ARI). (1.00)

b. LIST three (3) signals, or inputs, which will energize the i

" POTENTIAL ATWS" indicating light-(0.75)

c. STATE what is required to energize the " CONFIRMED ATWS" l

indicating light? (0.25) l

QUESTION 3.16 (1.00)

Concerning the recirculation pump seals; DESCRIBE the indications of failure for the-following;

a. The number one (1) seal

b. The number two (2) seal l

' QUESTION 3.17 (2.25) Concerning the Recire Flow Control Flux Estimator Circuit; l

a. STATE what conditions will cause the circuit to automatically shift to the actual APRM signal.

(1.00) I

b. STATE what conditions will cause the circuit to automatically shift to the estimated flux signal.

(1.00)

c. The FLUX ESTIMATOR NEEDS MAINTENANCE light becomes illuminated on panel P680. STATE what this indicates.

i i (***** END OF CATEGORY 03 *****)

-4. PROCEDURES - NORMAL.-ABHQBMAL, EtfERGENCY-AND PAGE 18 BAD 19LOGIDAL_Q9EIBQL QUESTION 4.01-(1.00) Essential 120 volt bus EK-1-Al is lost. STATE how the following ventilation dampers are effected (FAIL OPEN, FAIL CLOSED, FAIL-AS-IS)

a. Diesel Generator Building Ventilation Room A dampers (1M43-F020A and 1M43-F220A).

b. Diesel Generator Building Ventilation Recirculation' dampers (1M43-F030A, 1M43-F031A, 1M43-F230A and 1M43-F231A).

QUESTION 4.02 (2.00) A TOTAL LOSS OF OFF SITE POWER has occured. STATE the automatic ~ cctions which take place for the following;

a. Emergency Diesel Generators i

b. Reactor Recire Pumps

c. MSIV's

d. Reactor Water Cleanup QUESTION 4.03 (2.00)

The Control Room has become UNINHABITABLE and reqires personnel i ovacuation. LIST four (4) of the six (6) immediate actions to be taken prior to leaving the control room, in accordance with ONI C61 g " Evacuation of the Control Room". QUESTION 4.04 (1.00) On a reactor scram, if a SRV has LIFTED, or THE RELIEF SETPOINT IS BEING APPROACHED,-LIST two (2) actions to be taken to protect plant personnel. I (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) w__--__-__

l l' 4. 'EBQQEDUBES - NORMAL _. AHHQBti&L. EMERGENCY AND PAGE 19 B&DlQLQQ1QAL' CONTROL l l QUESTION 4.05 (1.50) Concerning a plant cooldown after reactor' shutdown by boron' injection; j

a. STATE why the cooldown rate is limited to 50 F/hr as compared to 100 F/hr on a normal cooldown.

b. How is the cooldown INITIATED and MAINTAINED at 50 F/hr?

QUESTION 4.06 (2.00) 4 Integrated Operating Instruction, IOI-3 " Power Changes" specifies reactor power shall not exceed 100% steady state over an eight (8) hour period. However, exceeding 100% power is permitted for short periods of time. For the power levels listed below, STATE the length of time power is permitted to be at the level indicated.

a. Greater than 102%

b. 102% c. 101% d. 100.5% i QUESTION 4.07 (1.50) The reactor is operating at 60% power _when the reactor pressure rogulator fails closed. LIST the three.(3) immediate operator actions required by ONI-C85-1" Pressure Regulator. Failure Closed". (Assume the Alternate Regulator is not available and the reactor does not scram) (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

4. 'kBQQEDURES-NORMAL ABNORMAL. EtfEBGENCY-AND 'PAGE-20 RADIOLOGICAL CONTROL QUESTION 4.08 (1.50) .For'the loss of a Reactor Feed Pump, answer the following in accordance with ONI N-27 "Feedwater Pump Trip".

a. LIST the IMMEDIATE ACTIONS for the loss of one.(1) Reactor Feed Pump (RFP) at 100% power.

l b.LASSUME the feed pump is determined to be inoperable. STATE the restrictions placed on reactor power level due to the loss of the feed pump? (Assume the Motor Feed pump is available)

a. STATE the restrictions on reactor power if one (1) Reactor Feed Pump is lost and the Motor Feed Pump is unavailable l

I QUESTION 4.09 (1.00) While reducing power in accordance with Integrated Operating Instruction IOI-4L" Shutdown", the. REACTOR MODE SWITCH is moved to the STARTUP AND STANDBY position.' STATE what affect this has on the APRM rod block and scram settings? I QUESTION 4.10 (1.00) 1 Concerning Refueling Operations at Perry Nuclear Power Plant; a. Define REFUELING MODE-

b. STATE the REACTOR MODE SWITCH position / positions during refueling?

QUESTION 4.11 (2.00) f >4 9 fco v& .\\ Concerning; containment t;;c.pe.aLuti control;

a. STATE the entry conditions for entry into containment pressure h

control.

b. STATE the action / actions required to control containment pressure

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) l

.4. 'PROCEDUBES - NORMALCABHQBMAIu__.EMEBGEHQY AND 'PAGE 21-RADIOLOGICAL CONTBQL i QUESTION.. 4.12 ~(1.50). . STATE ~the entry level conditions for drywell and containment hydrogen control. ' QUESTION 4.13' -(1.75) Concerning the' Safety Tagging Procedure; a. STATE what is' indicated if a circuit breaker for a piece of

equipment has 1r YELLOW TAG installed.

(0.25) 'b. STATE and. EXPLAIN, any procedural violation if the yellow tag 'is the ONLY. tag on the breaker in "a" above. (0.50)

c. Define a1 SWITCH CAP. (

(0.25).

d. What COLOR can a switch cap be?

(0.25) 1 e.WHERE and WHEN would a switch cap be used? (0.50) ] l l l l l i (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) o

c ~4'. PRQQEDDBES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 22 RADIOLOGICAL _QQBIBQL QUESTION 4.14 (1.50)- Fcr the definitions in column I, SELECT the correct item f rom the list ~ .in-column II..(NOTE; an item in column-II may be used.more than once) COLUMN:I COLUMN II

a. An electrical lead that shorts

1. Temporary control out a normal circuit function device

b. A sliding link that has been

2. Lifted lead opened'

c.. Temporary instrumentation left

3. Maintenance Safety installed for testing outside Block an approved and working Work

. Order,

d. An electrical connection to

4. Mechanical Foreign a temporary power supply Item

e. A blocked relay.

5. Jumper f.' Items not normally in the containment, that will' remain there while operating'in Modes 1, 2 and 3.

= QUESTION 4.15 (1.00) /Ess' N STATE two(2) of the h=: (/) lundi t _., s. :. '. t!... r-itu re d f or Im.ct.. r T';.. .w '/ ;. 0:,ntrc1 l 00:0T10t;

C

1. '/ 5 )

LIST the ENTRY LEVEL CONDITIONS for PEI-B13 " Reactor Pressure Vessel Control" l (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) -ii i .r .i. m

4. EPROCEDURES. - NOBth_ABHQRMAL'. EtEBGENCY AND -

PAGE 23-B&DIOLOGICAL CONTBQL ( QUESTION 4.17 (1.00) .The Perry Technical Specifications Surveillance Requirements specify CHANNEL CHECKS, CHANNEL 1 CALIBRATIONS and CHANNEL FUNCTIONAL TESTS to be p3rformed at. periodic intervals for the Reactor Protection System j Instrumentation. DEFINE the following; a. Channel Check-(0.25)

b. Channel Calibration (0.25) j

c. Analog Channel Functional Test.

(0.25) '. Bistable Channel Functional Test. (0.25) d i l I [ j J 1 1 (***** END OF CATEGORY 04 *****) (************* END OF EXAMINATION ***************) l L

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• F = 9/5'C + 32 Heat of'. fusion = 144 Stu/lbm
• C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-lbf 1 ft. H 0'= 0.4335 lbf/in. 2

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r I Table 3. Supe 7 heated Steam Ab5 Prest LDl50 in $8t. $at. hm0ersture-Desrees Fahrenheit. (541. Iem0) Water Steam 200 250 ' 300 - 350 880 850 500,800 700 800 let - 1000 litt 1200 g Sh 98 26 let 76 198 26 248 26 798 76 34826 398 76 498 26 598 26 698 16 798 26 894 76 998 76 1998 76 v 0 01614 3336 392 5 422 4 452 3 4821 Sit t 541 7 571 5 631 1 690 7 150 3 809 8 869 4 919 8 988 6 I101 74) h 69 13 1105 8 11502 1872 9 - 1195 7 1218 7 12448 12658 1248 6 1336 1 1384 5 1433 7 1483 8 1534 9 1546 8 1639 7 & l326 1.9701 2 0509 2 0841 2.1152 2 1445 2 8722 2 ;985 2 2237 22708 2.3144 2 3551 2 J934 2 4296 2 4648 2 4969 54 3776 8776 13776 187 76' 237 76 28776 337 76 43776 537 76 637 76 737 76 837 76 937 76 1037 76 I 0 01641 7353 78 14 84 21 90 24 9675 102 24 108 7) 114 21 12615 138 08 150 01 168 94 173 86 185 78 19770. e 0 62 241 h 130 70 1138 1 18486 1871 7 1194 8 1218 0 12413 1264 7 1288 7 1335 9 1344 3 14336 ' I4837 1534 7 1584 7 1639 6. 8, 0 2349 1 8443. l.8716 1 9054 19369.19M4 1.9943 2 0708 2 0460 20H7 2 1369 2 1776 2.2159 22521 216M 2 3194 I4 Sh 4 79 56 19 106 79 1 % 19 706 79 256 79 306 79 406 79 506 79 606 79 706 79 806 79 906 79 1006 79 v 0 016H 3842 38 84 4893 44 98 4802 5l 03 54 04 5704 6303 69 00 74 94 00 94 46 91 92 87 98 84 0 93 213 h 141 26 1143 3 1146 6 1170 2 11937 1217 1.l?40 6 1264 1 1287 8 ' 1335 5 13840 14334 1483 5 1534 6 1586 6 16J9 5 s 0 2836 13819 1J928 L8213 1.8593 1 8892 1 9473 1 9439 1 9697 2 01H 2.060J 2 10!! 21394 - 2.!?$7 2.2101 2 1430 54 38 00 88 H 138 00 188 00 238 00 288 N 388 00 488 00 588 00 684 00 788 00 888 00 988 00 lille v 8147 76 799 73 67 30 52 37 60 34 67 36 72 38 71 42 86 46 93 Sl 00 M 06 59 13 63 19 ' 67 75 Ql200s k 180 17 1150 5 1164 8 1191 6 1216 3 1739 9 17636 12874 1335 7 13818 14:1 7 1443 4 1534 5 1546 5. 1639 4 s .J121 - 31%8 I J833 1 8158 l 8459 1 8743 L 9010 1 9265 l 9139 2 $l71 ~ 2 8585 2.9969 213J2 2 1616. 2 2004 Sh 36 97 8s 97 136 97 18697 236 97 28697 386 97 48697 58697 64697 786 97 88697 98697. 18 0 01473 76 790' 77 837 79 899 - 31 939 33 9H 35977 31 985 41986 45978 49964 53 946 57926 61 905 65 887 v G13 031 181 21. 1150 9 1168 7 1197 5 1216 2 1239 9 1763 6 1287 3 1335 7 1383 8 1433 7 1483 4 1534 5 1586 5 16394 s 0 313? 13 % 2 1 7809 1 8134 3 8437 1 8120 1 8988 1 9242 1 9117 20155 20%3 2.0946 2 1309 2 1653 ' 2 1987 Sh 72 04 72 04 ' 172 04 17704 ??2 04 272 04. 377 04 47204 577 04 672 04 77? M 872 04 977 04 y 0 01683 20 087 20 in8 ?? 3% 23 900 75 478 76946 78 457 31 466 34465 37458 40 441 434)$ 46 470 '49 405 g21961 h 1 % 21 11 % 3 18671 1891 4 1715 4 1739 2 12610 1286 9 1334 9. 13:3 5 1437 9 - 1483 7 1514 3 l%63 1639 3 s 0 3358 4 7320 1 7475 1 7805 181ll 1 8397 ' 1 86 % 1 8921 1 9391 1 98 % 2 0?44 2 0678 2 0991 2 1336 21665 25 H3 5H3 09 H 15H3 20H3 2H H 35H3 45Hl 199s4 SH H 65H) 7% H SM - MH] G40 04' 0 01693. 16 101 16 H8 Ila?9 9 076 70 int ti ssi 77 740 75 1s3 ti ng 3; us 34 740 37 110 39 g18 h 704 5/ l16816 . 1864 6 li'vi 7 714 4 1714 % 1767 5 1746 4 11:46 114 t 1 14171.14A lo ist4 7 - Isa4 7 141u t 0 J53s I lid t i 7747 I is41 i 74 % i al4s 1 441% i n617 l 9149 9saa i vi97 7 Gial 7 0/44 7 inre 7 4414 -1 Sh 4966 99 % 14H6 99 66 749 % 349 % 44966 549 66 64966 749 66 849 66 9J9 % 38 v- 0 01701 13 744 le sio 15A59 16 891 7 914 18 929 70 445 77 951 74 9$7 76 949 28 *43 30 9 % 37 4'1 G50 348 h 718 93 llW I 1181 0 1283 6 12378 261 9 17n6 0 1314 7 1383 0 14325 1482 8 1534 0 1586 t' 1639 0 e s 0 3682 1 6995 1 7334 1 7647 1 7937 8210 1 6461 1 8946 19386 1 9195 2 0179 2 0543 2 0848 2 1217 i 35 Sh 40 71 90 71 140 ?! l 90 71 740 71 340 71 44071 540 71 64071 740 71 840 71 940 71 0 01708 11 896 2 654 13 % 2 14 453 5 334 16 707 17 939 19 662 21 ??9 23 092 to 403 76 517 78 700 059 291 h 228 03 1167 1 187 8 pQ / 12371 241 3 'l?85 5 ID39 1382 8 1432 3 1482 7 1531 9 1586 0 1638 9 8 0 3809 14812 1857 174t 51161. 8035 1 8294 1 8774 1 9214 1 % 24 2.0009 2 0312 2 0117 7 1046 Sh 32 75 82 75 132 75 82 75 232 75 332 75 43??5 532 75 632 75 732 75 (32 75 932 75 83 0 01715 C97 ' 1036 11 838 12 6?4 3398 14 8 % 15685 17195 18 699 20 199 21697 23 194 24 689 1 v 067 m 1 .n 236 14 1169 8 186 6 1211 7 1236 4 260 8 1285 0 1333 6 1382 5 1432 1 1482 5 1533 7 1585 6 1638 8 s 0 3921 16765 6992 1 7312 1 7608 : 788J 18143 1 8624 19065 1 6476 1 9860 2 0224 20%9 2 0899 45 A4 25 56 75 % ID % 175 56 -225 % 325 % 425 % $25 56 625 56 ?!$ 56 825 % 925 % Q14 4li e 0 01721 9 399 9 777 10 497 1 e Pt 11 892 !! 577 13 932 15 276 16 614 17 950 19 282 20 613 f t 913

1. 243 49 1872 i

!!85 4 1210 4 1235 1 1260 2 1284 6 1333 3 1382 3 1431 9 1482 3 1533 6 1585 7 1638 7 8 0 4021 1 6671 1 6849 1J173 1 7474 13748 1 8080 1 8492 1 8934 l.9345 1 9730 2 0093 2 0439 7 0768 H gn. 18%8 68 98 11898 168 98 21898 318 98 41898 518 98 618 98 718 98 818 98 918 98 08102) v 0 01727 8 514 8 769 9474 80 062 10 688 19 306 17529 13 ?4i 84947 16 150 17350 18 549 19 746 h 15623 1174 1 1184 1 !?09 9 1234 9 !?59 6 1284 1 1332 9 1382 0 1431 7 1482 2 1533 4 1585 6 16386 s 04:12 16586 16120 1 7048 11349 13628 1 7890 1 8374 1 8816 1 9227 1 9613 1 9917 2 0322. 2 0652 59 Sh l? $1 $P 93 l12 93 162 93 2 293 31293 412 93 Sit t) 612 93 312 93 812 93 912 91 0810h v 0 01733 7 945 8546 9 130 9 702 to 767 11 388 12 485 13 583 la 677 15 769 16 859 17 948 h 256 4) lit? 9 1708 9 1234 2 1259 I. 1283 6 1332 6 1381 8 lin 5 1882 0 1533 3 1585 5 1638 5 s 0 4L96 8 6601 1 6933 1 7237 I 7514 1 7781 8 4266 L 8710 1 9121 1 9507 1 991 2 022 20% 88 th 7 29 5729 10729 157 29 '20729 307 79 407 ft 507 ft 60729 707 29 to? 79 90729 092 ill 0 01738 7 174 2 r57 7 815 8 354 8 8 Al 9 400 10 475 11438 12 446 13450 14452 15457 16 450 h 262 21 1117 4 litt6 I?04 0 1233 5 1758 5 !?83 2 1332 3 1381 5 1431 3 1481 8 1533 2. 1585 3 1638 4 s 04273 1 6440 1 6492 16829 1 7134 1 7417 1 1688 1 8168 1 8612 1 9024 1 9410 1 9774 2 0l20 2 0450 SA 2 07 52 02 102 02 157 02 702 02 302 07 4020? 50202 607 02 702 02 8020? 90202 85 , 0 01743 4653 6 675 7195 16tt 8186 8M7 OIS 10 55? ll 444 17 412 13337 14 761 15 183 0 17 983 h 76763 1679 i 1640 3 I?070 123? I I?si 9 128? 7 4 J119 1341 3 14311 leal 6 15330 158% 2 1638 3 s 0 4344 1 6375 16390 1 6731 3 7040 1 7324 1 1590. 1 8077 8 8522 1 8935 I 9321 1 % 85 2 0031 2 0361 Sh 4707 9707 14101 19707 79707 39707 49707 59707 69707 19707 89707 78 0 0l?48 6 205 6 664 71?J 7 590 8 039 8 972 9 793 10659 18 527 12 382 11 740 14 057 002 9J) h 272 74 1180 6 1206 0 121: 1 !?573 1782 2 1331 6 1381 0 1430 9 1481 5 1532 9 1585 1 1618 2 s 0 6411 -1 6316 i M40 1 6951 1 1237 1 7504 4 1993 184J9 8 4852 1 9738 1 9603 1 9949 2 0279 $h 4239 9739 142 39 197 39 29? )9 39239 492 39 592 39 692 39 792 39 892 39 F1 s ' 00l?S3 5 814 6 7J4 4 645 7 674 749 8 320 9tM 9 945 10 750 II H3 12 3H 11 1 % 007 El) n 27756 1181 9 120s 0 12312 I?% 7 1281 7 1331 3 1390 7 1430 7 1881 3 1%?7 1585 0 6638 1 6 0 4414 1 6260 16u4 1 6868 1 71 % 1 7424 1 1915 1 8361 1 8774 .I 9161 1 9526 I 9812 2 0202 Sh = superheat. I h = enthalpy. Blu per Ib v = specific volume CU f t per Ib 5 - entropy. Blu per R per Ib g } l 1 B -3 J

l ) L l l Table 3. Superheated Steam-Continued Aos Pres 8 t07$g in $81 $4l km04#4twe - De8rees f ahrenheit Get 14m0) 'h 8t et $le8m ISO 800 ~ 450 500 550 800 200 000 800 1100 1100 1200 1300 1430 Sh 3796 4796 13796 18798 237 96 28796 38796 48796 58796 68796 78796 88796 98796 108796 88 s 0 01757 $ 471 $ 801 4 214 6 627 7 018 J act 7 794 8 560 9 319 40 075 10 829 11 54l 12 331 13 04 01204) h 282 15 1183 1 1204 0 1210 5 12s6 1 1211 3 1306 ) 1330 9 1340 5 1430 $ 1481 1 IS32 6 1584 9 16 8 (L4534 1 6204 1 6413 1 6790 81080 1 7349 1 7602 11842 1 8289 13702 1 9089 1.9454 1 9800 2 0 54 33 74 8374 13374 181 74 233 74 283 14 38374 48374 583 74 683 74 78374 883 74 983 74 1083 74 85 e 0 Ol?62 5 167 6 445 $ 840 6 ??) 6 597 6 966 7 330 8 0$2 8 768 9 480 to 190 10898 il 604 12 Jio 13 0 016241 h 286 S2 1184 2 1203 0 1229 7 12$5 S 1280 8 130s 8 1130 6 1380 2 1430 3 1481 0 1531 4 1584 7 1 8 0.4590 1 6159 1 639/ 1 6716 1 7008 13279 I M32 1 7772 1.8220 1 8634 1.1021 1.9346 1.9 73 ) 2 Sh 29 72 79 12 129 12 879 72 229 12 279 72 319 72 479 72 579 72 679 72 179 72 871 72 979 72 101 98 e 0 01766 4 895 5 128 5 505 5 869 6 223 6 572 6 917 7 600 8 277 8 950 9 62 10 290 10 958 al 425 02028) h 29069 1185 3 1202 0 1218 9 IM49 1280 3 13c5 4 1330 2 1380 0 1430 1 1480 8 1532 3 1584 6 1637 8 1 s 0 4643 1 6113 1 6323 1 6646 16940 1 1212 11647 I 1707 1 8156 1.8570 1 8957 1.9323 19669 2 00 $h 2%87 7587 12%$7 17587 27t 47 27% 87 37$87 47% 87 67587 67587 77187 87587 97587 107587 95 e 0 01770 4 651 4 845 5 70% 55%I S 489 6 nt 6 %48 7 196 3838 8 477 9 113 9 747 10380 11 012 Il u) 024 131 h 294 70 1186 2 1200 9 1228 1 12483 1279 8 130$ 0 1329 9 1379 7 1479 9 1440 6 l$32 8 1584 5 163 s 0 4694 16069 1 6253 14580 16876 1 7149 1 7404 1764$ 1 8094 1 8309 1 8497 1 9262 1 9609 1 9940 Sh 22 18 72 18 12218 !?218 222 18 21218 37218 47218 572 18 6721;l 772 18 87218 97218 1072 18 188 e 00l??4 d ell 4 590 den S 766 5 588 6 904 6 216 6 833 7443 8 0$0 8 655 9 254 9 860 10 460 11060 02782) h 298$4 ll87 2 1899 9 12274 IM37 1279 3 1304 6 13M 6 1379 % 1429 7 1880 4 th32 0 1 844 16376 169 8 04743 1.6027 4.6187 I65!4 1 6814 1 2088 1 1344 11586 88036 3 8451 1 8839 I 9205 I 9652 1 9143 2 $h 1863 $$ $3 11463 16463 218 63 26863 36861 468 63 $68 63 668 63 76863 86463 968 63 1068 6 195 e 0 01778 4 231 4 359 4 690 S 001 6 315 5 617 5 91$ 6 504 7 086 7 645 8 24l 8 816 9 389 9 %l 10 532 0313h h 302 24 1184 0 8198 8 1226 6 1253 1 1278 8 1304 2 1329 2 1319 2 14294 1480 3 IS318 1584 2 16375 1 s 04190 15988 1 6122 (64$5 1 6765 1 7031 1 7288 1 7530 l) 981 18396 1 8785 1 9161 1 9494 19828 2 $h l$ 2l 6% 2l ll% 71 16% 2l 28% 71 741 21 36% 71 46% 21 $6% 21 66% 21 76%2l 86% 2l 96% 78 106% 110 v 0 01787 4048 4149 4 4E4 4 777 6 068 S E1 SH1 6 705 674 7 314 1 A6% $ 411 8 948 9 %07 10 0%) 0 34 791 h 30% 40 llH 9 liti 7 177% 8 17%7 % 1714 3 13018 137a 9 1379 0 14h / 1440 1 Illi 7 1584 6 16374 1698 4 1746 a 04434 159$0 1 6068 1 6396 1 6694 16915 1 7233 17e4 1 7924 18344 18732 1 9099 4 9446 1 9777 2 0093 2 Sh, 1192 61 92 11192 161 92 211 92 26192 36192 46192 56192 66192 M192 861 92 96192 1041 92 lll 0 0178S 3 881 3 957 4 265 4 %8 4 641 5 119 $ 392 5 932 6 46$ 4 994 7 52L 8 046 8 570 9 093 9 615 03808) h 309 25 1189 6 1196 7 1225 0 AMit 1277 9 1303 3 1328 6 1378 7 14290 1479 9 153t 6 IS&4 0 16372 1691 4 17ag ) s 0 4477 1 5963 1 6001 1 6340 1 6644 1.6922 1 7181 174M 1 7811 1 8294 1 8682 1 9049 19J96 19727 2 0044 2 Sh 8 73 58 73 158 13 158 73 208 73 258 73 358 13 45873 % 8 71 658 73 758 73 858 73 958 73 1054 73 120 v 0 01789 3 7275 3 7815 4 0786 4 3610 4 6341 4 9009 51637 ! dl} 6 1928 6 7006 72060 2 7096 8 tilt 8 Filo 9 2134 0412h h 3I2 58 1190 4 1195 6 1224 l 1251 2 12774 1302 9 1328 2 L34 4 1418 8 1479 8 15314 1583 9 1631 1 1691 3 1746 2 8 04919 1 5819 1 5943 1 6286 16592 1 6872 4 71J2 1 7376 11829 1 8246 1 8635 1 9001 1 9349 .1 9680 1 9996 2 0300 Sh 287 5267 10247 IS2 67 202 67 25267 33267 45247 $52 67 65267 75267 85267 95267 1052 67 138 v 0 01796 34544 3 4699 37*89 4 0129 4 2672 4 6161 4 7589 5 23H $ 7118 6 1814 6 6486 21140 7576l 8 04 t l 8 5033 04733) h 318 95 1191 7 11934 1222 5 3289 9 1276 4 1302 1 13215 1377 9 14284 14794 1531 1 1581 6 16369 1691 1 1746 1 s 0 4994 1 5813 I S8J3 1 6182 1 6493 14715 170J 1 7283 1.7737 1 8165 18545 18911 1.9259 1 9594 1 9907 20211 Sh 46 96 96 96 146 96 196 96 248 96 34696 44696 54896 64696 14696 84696 946 96 1046 96 140 s 0 01803 3 7190 34661 37143 3 9526 4 1844 44119 4 8548 52nS 5 7364 $ 1709 6 6036 70349 1 4652 2 8946 05304) h 324 96 1193 0 1220 8 1248 7 1275 3 1301 3 1326 8 1377 4 1428 0 14791 1530 8 15814 1636 7 1690 9 17459 s 0 5071 1.5752 160M 1 6400 1 6686 3 6949 1 7196 l) 652 1 8071 1 8461 18128 1 9176 1 9504 1 9825 2 0129 sh 48 57 9157 14157 19157 241 57 34157 44157 S4157 64157 74157 441 57 94157 104t 57 i 118 e 0 01809 3 0139 32208 34%S 36799 3 8978 4 1112 4 5298 4 9428 $ 3507 S 1568 4 1612 6 5642 6 9661 7 3A71 0 58 431 h 330 65 ll541 1219 1 12474 1274 3 1300 5 1326 1 1376 9 1427 6 1418 7 1530 S 1583 1 1616 S 1690 ) 1745 7 s 0 5141 1.5695 15993 1 6313 1 6602 1 6867 1 7115 1 7573 1 7997 1 8383 1 8751 1 9099 1 9431 1 9744 2 0052 Sh 36 45 8645 136 45 19645 236 45 33645 436 45 53645 636 49 73645 836 4% 93645 1036 45 185 s C 01815 2 8336 3 0c60 3 2288 34413 3 6469 3 8480 4 7420 4 6295 6 0132 53945 $ 774l 6 1522 6 $293 6 93 % 063551 h 336 07 l195 L 1217 4 1246 0 1213 3 1299 6 1325 4 1176 4 14272 1478 4 IS30 3 1582 9 1436 3 1690 5 17456 s 0 $206 1 $641 14906 1 6231 16522 16190 13039 13499 L 1919 1 8310 84678 1 9027 8 9359 l 9676 I 9980 $h 3158 81 58 Ill S8 181 58 23158 331 $8 431 $8 $3l58 631 58 731 58 43t 58 til S8 103158 178 e 0 01821 2 6738 28162 30?88 3 2306 3 4255 3 6158 3 9879 4 3536 4 7155 S 0789 S 4325 $ 7884 6 1440 44993 068 4D h 34124 11 % 0 12iS 6 1244 7 12722 1294 8 1324 7 137S 8 1426 8 14780 1530 0 IS8;6 1636 1 16904 1745 4 s 0 6269 1 5591 l 5823 14152 1 6447 1 6717 16968 1 7428 3 7850 1 824I i 8610 18959 1 9291 1 9608 1 9913 $n 26 92 76 92 12412 176 97 27692 374 97 476 92 52692 676 92 77692 876 92 9492 1024 12 108 v 0 01877 25312 2 6474 2 8508 3 0433 3 ??n6 34093 3 7671 4 1084 4 45c4 4 7907 5 1249 5 4657 6 8014 6 1351 0 73 081 h 34619 1196 9 1213 8 1243 4 1271 2 129' S 1324 0 1375 3 1426 3 14?? 7 1529 7 IS82 4 143% 9 1890 2 1745 3 s 0 5328 15543 1 $143 1 6078 1 6376 16647 16900 1 7362 1 7784 I 8176 I 3545 1 8894 1 9227 19545 l 9449 sh 2247 7247 12247 17247 22247 32247 42247 52247 62247 12247 87247 97247 10?? 47 199 e 0 0181) 24030 24961 2 6915 2 8756 J os?S 32146 3 % 01 3 8889 42140 4 5365 4 8572 5 1766 $ 4949 5 8t?4 1371 531 h 350 94 l197 6 1212 0 1242 0 1270 1 1797 8 1323 1 1374 8 len t 14774 1529 4 1582 1 16M 7 1690 0 1745 1 6 0 5384 4 5498 iSu? I 6006 66307 1 6581 1 6435 1 7299 1 7722 1 8115 1 8484 4 84J4 1 9166 8 9484 1 9789 14 1820 6A 20 lit 20 168 20 !!8 20 318 20 418 ?0 $18 20 618 20 718 20 Ill 20 til 20 1018 20 288 v 0 01819 2 2873 23%'8 2 $480 2 724 i 2 8939 3 0583 3 37A3 16916 4 0008 43077 4 6124 4 9165 S 2191 5 5709 0 81 801 li 3% $1 1198 1 1210 i 1240 6 17k9 0 1296 2 13776 1374 3 14M 5 14770 1579 ) 1581 9 16 h e 1689 8 174$ 0 s 0 5438 1 5454 1 $$. I 6938 1 6?42 1 6518 1 6773 112J9 1763 180$1 1 8426 i 8776 1 9109 4 9427 8 9712 Sh = Superhe81. I h = enthalpy. Blu per Ib V a $ptClflC Volumt, Cu fl per Ib 5 = ent10py Btu pet I pet Ib B-4

7 ,I. Table 3. Superheated Steam-Continued tf/5 ln Sat $al hapaNee de8m5 f ahrenheit (Sal. lemo) W41er Steam 448 854 568 554 130 200 000 000 1000 1100 1200 1300 1400 1580 $h - 14 09 64 09 114 09 164 09 214 09 314 09 414 09 514 09 614 09 714 09 814 09 914 09 1014 09 1114 09 218 v 0 01844 2 1822 ? ?364 24181 2 5840 2 7504 2 9078 3 7137 3 5128 3 8080 41001 4 3915 4 6411 4 9695 5 2571 5 5440 '. 1345 91) h 359 91' 1199 0 1208 02 1239 2 1268 0 1295 3 1321 9 1373 7 1425 1 1476 7 1528 8 1581 6 1635 2 1689 6 1744 4 1800 4 s 15490 1.5413 13522 1 5472 1 6140 1 6458 1 6715 1.7882 17907 1 8001 1 8371 1 8721 1 9054 1 9372 1 9677 1.9970 Sh 1012' 6012 110 12 16012 21012 310 12 41012 51012 41012 71012 81012 910 12 1010 12 1110 12 2M .e 0 01850 2 0863 2 1240 2 2999 2 4638 2 4199 2 7710 30642 3 3504 3 6321 3 9125 4 1905 4 4671 47426 5 0173 5 2913. 1349 881 h 364 17 lit 9 6 1206 3 1237 8 1266 9 1294 5 1121 2 1373 2 1424 7 1476 3 1528 5 1581 4 1635 0 1689 4 1744 7. 1800 6 ; a 0.5540 13374 1.5453 1 5404 1 6120 1 6400 1 6658 1 7128 11553 119e8 1.8318 1 8668 1 9002 19320 1 9625 1 9919 $h ' 6 30 56 30 106 30 1 % 30 206 30 306 30 406 36 506 30 606 30 706 30 806 30 906 30 3006 30 1106 30 IN - e 0 01855 1 9985 2 0212 21919 2 3503 2 5008 2 6461 2 9276 32c20 34726 3 7406 4 0068 4 2717 4 5355 4 7984 5 0606 i , 1393 701 h 368 28 1200 l 1204 4 1236 3 1265 7 1293 6 1320 4 1312 7 1424 2 1416 0 1528 2 1581 I 1634 8 1689 3 1800 5 l 1 8952. 1 9271, '1744 5 s 0.5588 13336 1.5385 1 5747 13062 4.6344 1 6604 13075 13502 11897 18268 1 8618 1 9576 1 9869 .I Sh 2 61 52 61 102 61 !$261 20261' 30261 402 61 502 61. 602 61 ' 702 61 802 61 902 61 1002 61 1102 61 748 s 0 01860 1 9177 1 9268 20918 2 7862 2 3915 2 5316 2 8024 3 0661 3 3259 3 5831 3 8385 4 0976 4 34 % 4 5477 4 8492 1391391 h 372 27 1200 6 12024 1234 9 1764 6 1792 7 1319 7 1372 I IA238 1475 6 15279 1580 9 1634 6 1689 I 4744 3 1800 4 s 0.5634 83299 15320 15647 1 6006 13291 18552 1 7025 1 7432 IJ844 1 8219 18570 1 8904 1 9223 1.9528 1 9822 Sh - 49 03 ^ 99 03 149 03 199 0) 219 03 399 03 49903 $9903 69903 799 03 89903 999 03 1099 03 298 e 0 0t865 8432 2 0016 2 1504 2 2909 2 4262 2 6872 2 9410 31909 34382 36837 3 9278 4 1709 4 4131 4 6546 H0094 h 376 14 201 1 1233 4 1263 5 1291 8 1319 0 1378 6 1423 4 14753 15216 1580 6 1634 4 1688 9 1744 2 1800 2 s 0 % 79 5264 13629 1.5951 1 6239 1 6502 1 6976 53405 1 7801 18173 1.8524 1 8858 1 9177 1 9482 1.9776 Sh 4556 95.56 14556 195 56 295 56. 395 56 495 56 595 56 695 56 79556 895 56 995 56 1095 56 268 v ' 0 01870 1 7742 9173 2 0619 2 1931 2 3289 2 5608 2 8256 3 0663 3 3044 3 5408 ' 3 7758 4 0097 4 2417 4 4150 H04 441 h 379 90 1201 5 231 9 1262 4 1790 9 1318 2 137I i 1423 0 1474 9 1527 3 1580 4 1634 2 1688 7 1744 0 1000 I s 4 5122 13230 .3573 1.5899 1 6189 1.6453 1 6930 1.7359 1 7756 1.8124 1 8480 1 8414 19173 1 9439 1 9732 Sh 42 20 92 20 14220 192 20 292 20 397 20 492 20 59220 692to 79220 892 20 992 20 1097 20 e 214 e 0 01875 1 7101 8391 1 9799 2 1171 ? ?388 24874 2 7186 2 9509 3 1806 3 4084 36349 3 8603 40849 4 3087 i H07 801 h 383 56 1201 9 230 4 1261 2 1790 0 1317 5 1370 5 1427 6 1474 6 1527 6 1540 1 1634 0 1688 5 17419 1800 0 { t 0.5164 13197 5518 1 5848 1.6140 1 6406 1 6845 1 7315 1 7713 1 8065 1 8437 1.8771 1 9090 19J96 1 % 90 4 I Sh 38 93 88 93 13893 18893 288 97 388 93 488 93 58893 68893 788 93 88893 98893 3088 93 288 e 0 01880 .6505 Hil 071 h 38712 202 3 ..7665 9037 2 0322 2 1551 2 3909 2 6194 2 8437 3 0655 3 2855 3 5042 3 7211 3 9384 4 1543 228 8 260 0 1289 1 1316 8 1370 0 1422 1 1414 2 1526 8 1579 9 1633 8 1688 4 1743 7 17998 s 0.5805 .5166 ' 3464 .5798 13093 16361 1 6841 11273 11671 13043 1.839% 1 8730 1.9050 1 93 % 1 9649 Sh 35 75 85 75 35 75 185 75 285 75 385 75 485 75 585 75 685 75 785 75 885 75 985 75 1085 15 298 e 0 01885 15948 6988 18327 9578 2 0772 2 3058 2 5269 2 7440 2 9585 3 1711 33824 3 5926 3 8019 4 0106 H14 25) '. b 390 60 1202 6 227 3 1258 9 288 1 1316 0 1369 5 1421 7 1473 9 1526 5 1579 6 1633 5 1688 2 1743 6 17997 8 0 5444 15135 3412 157V 6048 1 6317 1.6799 11232 11630 1 8003 18J56 1 8690 1.9010 1 9316 1.9610 Sh 3265 ' 8265 132 65 18265 28265 38265 48265 58265 682 65 78265 882 65' 982 65 1082 65 I 188 e 0 01889 1 5477 1 6356 1 7666 1 8393 2 0044 2 2263 2 4407 2 6509 2 8585 3 0643 32688 3 4721 ' 3 6746 3 8764 Hl1J5). k 39399 12W 9 1275 7 US' 7 12812 1315 2. 1368 9 1421 3 1473 6 1526 2 1579 4 M13 3 1688 0 17434 17996 s 0 5882 1 5105 1 5351 i S203 1.6003 1 6214 ~ 16754 13192 1 7591 13 %4 1 8317 1 8652 1 8972 1 9278 1 9572 Sh 29 64 79 64 ' 29 64 ?9 64 279 64 379 64 47964 579 64 679 64 779 64 879 64 97964 1079 64 318 e 0 0l894 1 4939 1 5763 1 7044 r?3) .9463 2 1520 23600 2 5638 2 1650 2 9644 3 1625 3 3594 3 5555 3 7509 1420 367 h 39730 1703 2 1224 8 12 % 5 141 314 5 1368 4 1420 9 147J2 1525 9 1579 2 1633 1 1687 8 1743 3 17994 8 0 5920 1 5076 1.5311 13657 s5960 ,6233 16719 11153 1 7353 1J927 1 8280 1 8615 3.8935 1 9248 1 9536 Sh 2669 76 69 26 69 176 69 27669 376 69 476 69 57669 676 69 77669 87669 97649 1076 69 129 v 0 01899 1 4480 1 5?07 1 6462 7623 3 8725 2 0813 22843 24821 26774 2 8708 3 0628 3 7538 3 4438 3 6332 H23.31) h 400 53 IK34 1222 5 1255 2 .285 3 1313 7 1367 8 1470 5 1412 9 1525 6 1578 9 1932 9 1687 6 1743 l 1799 3 s 0.5956 13048 1 5261 1 % 12 .5918 1 6l92 1 6640 IJill 11516 11890 1 8243 1 8579 1 8899 1 9206 1 9500 Sh 2342 73 82 123 82 7382 27382 373 82 473 82 573 82 47382 77382 87382 973 82 1073 82 338 e 0 01903 14048 146s4 1 5915 1 7050 8125 2 0168 2 2132 2 4054 2 5950 2 7828 2 9692 31545 3 3389 3 5227 H2618) h 40370 1203 6 1220 9 1254 0 1744 4 3 30 1367 3 1420 0 1472 5 1525 3 l578 7 1632 7 16875 1742 9 1799 2 s 0.5991 13021 1 5213 1.5%8 1 5876 t 6153 1 6643 13079 13480 13855 1,8208 1 8544 1IL464 1 9171 1 9466 Sh 21 01 fl 01 21 01 71 01 271 01 371 01 47101 571 01 671 01 771 01 87101 97101 1071 01 349 e 0 01908 13640 1 4191 15399 6511 7561 1 9552 21463 2 3333 2 5175 2 7000 2 8811 3 061) 3 2402 3 4186 i 1428 991 h 406 80 120J 9 1219 2 1252 8 '283 4 ' 31? 2 1366 7 1419 6 1472 2 1525 0 1578 4 1632 5 16873 1742 8 17990 s 0.6026 84994 1 5165 1.5525 .6184 1 6606 11044 17445 1 7820 1 8874 18510 1 8836. 1.9138 1 9432 LS836 Sh 18 27 6477 18 27 6427 26827 368 27 46A 27 564?? $6A 27 768 27 8611 27 968 27 106A 27 358 - v ' 0 019t2 1 3255 13125 1 4913 6002 7078 1 8970 2 0832 2 7652 24445 2 6719 2 7980 29730 3 1471 3 3205 . HJ173) h 409 83 1204 0 1217 5 1751 5 282 4 311 4 1366 2 1419 2 1471 8 1524 7 1578 2 1632 3 1687 1 1742 6 1798 9 8 0 6059 14%6 13119 1 5483 ,5197 6077 16571 11009 1 7411 11787 1 8341 1 8427 18798 1 9105 1 9400 Sh 1559 6559 15 59 65 59 265 59 36559 44519 56559 66559 76559 86559 965 59 1065 59 380 e 0 01917 1 2891 1 3285

4454 557) 6525 1 8471 2 0237 2 2009 2 3755 ? $482 2 7196 2 8898 3 059t 3 2779 H34 4ll h

41281 170 1 1215 8 250 3 281 5 310 6 1365 6 1418 7 1471 5 1524 4 1577 9 1632 1 1686 9 1742 5 !?98 8 s 0 6092 14943 1507J , 544 l 5158, 6040 1 6536 1 6976 1 1379 11754 1 8109 18445 18766 I 9073 1 9368 Sh 10 39 6039 10 39 60 39 260 39 340 39 46' 39 % 0 39 640 39 76039 860 39 960 39 1060 39 384 v 0 01925 12218 1 2472 I J606 4635 5598 1 7410 i 9139 2 0825 2 2464 2424 2 5750 2 7366 2 8473 3 0572 H39 6ll h 418 59 1204 4 1212 4 12477 279 5 309 0 1445 1417 9 1870 $ 1523 8 1577 4 16316 1686 5 1747 2 1794 5 s 0 6156 14894 14982 1 5360 i H83 ,5969 1 6470 1 6911 1 7315 1 7612 18047 1 8384 18105 1 9012 1 9307 Sh = Superheat. I h = enth8lpy. Blu per lb y = specibe v0lume, cu ft per Ib s - entropy. Blu per R per Ib I B -5

I f 1 Table 3. Superheated Steam-Continued ADS Press Lb/$0 le. $81. $81. Itmperalwl-Degree 9 f 8htenheit (Sat. temot t"alef $ team 450 580 558 800 Ils 280 800 Alt 1800 lite I200 ' 1300 1480 1508 1h S 40 5540 '0540 15540 20540 25540 35540 45540 55540 65$40 75540 855 40 955 40 10$$ 40 488 e 6 01934 16 10 6 1734 l 2641 1 836 14763 1 % 46 1 6499 1 8151 19759 2 1139 2 2908 2 4460 2 5987 2 7515 2 9037 H44 60) 6 424 17 204 4 1208 8 1245 1 ;277 5 4307 4 1335 9 1363 4 1417 0 14101 1523 3 1576 9 16312 1686 2 174l 9 1798 2 8 0 6217 .4847 1 4894 1 5282. Sell i Stol I 6163 1 6404 1 6850 11255 1 7632. 11988 1 8325 18647 I 8955 1.9250 Sh 60 SO 60 100 60 50 40 200 60 25060 350 60 450 60 550 60 650 40 750 60 850 60 950 60 1050 60 424 e 0 01942 1 6057 1 1071 2648 1 3113 4007 14856 1 5676 1 7258 1 8795 2 0304 28795 2 3273 24739 2 6196 2 7647 H49 401 h 429 56 1204 7 1205 2 242 4 12754 305 4 1334 5 1362 3 1416 2 1469 4 1522 7 1576 4 1630 8 1685 8 1741 6 1798 0 8 0.6276 1 4802 1 4808 3206 15542 58JS 1.4100 16345 1 4791 11197 11575 119J2 1 8269 8.8591 1 8819 1.9195 Sh 4597 9597 4597 9597 24597 34597 44597 54597 64597 74597 84597 94597 1045 97 448 v 0 01950 0554 llSlf 1 2454 3339 4138 1 4974 16445 1 7918 1 9363 2 0790 22203 2 3605 24998 2 6384 H54 03) h 434 77 204 8 1239 7 17734 304 2 333 2 1361 1 1415 3 1468 7 1522 I IS7S 9 1630 4 1685 5 1741 2 17977 s 06332 4759 1.5132 1.5474 4712 6040 4 6284 1 6734 1 7142 11521 11878 1 8216 1 8538 1 8847 1 9143 Sh 4150 91 50 14150 9150 241 50 341 50 44 t S0 5415? 641 50 741 50 84150 941 50 1041 50 888 = 0 01959 1 0092 1 0939 1 1852 1 7691 3482 14242 1 5703 1 7117 18504 1 9872 2 1276 2 2569 2 3903 25?)0 Hit 50) h 43983 1204 8 1736 9 1271 3 1302 6 331 8 1360 0 1414 4 1468 0 IS7! S 1575 4 1679 9 1685 1 1740 9 17974 s 0 6347 1 4718 1.5060 1 5409 15711 5982 1 6230 8 6680 11089 1 7469 1 7826 18166 1 8488 1 8797 1 9093 Sh 3718

• 8718 37 18 8718 23718 33718 43718 53718 63718 73718 83718 937 18 1017 18 488 v 0 01967 0 9668 1 0409 1 8300 2116 2881 13615 15023 16384 1 7716 1 9030 20330 2 1619 2 2900 2 4173 6462 821 h

444 75 1204 8 1234 1 1269 1 300 8 3 30 S 1358 8 1413 6 14673 1520 9 1674 9 1629 6 1684 7 1740 6 17972 s 0.64J9 3 4617 8.4MO I 5346 s % 52 . $925 1 6176 1 6628 1 7038 1 7469 11777 iSill I 4439 1 8744 1 9045 Sh 32 99 4799 32 99 18299 232 99 332 99 43799 51299 63299 732 99 832 99 932 99 1032 99 le8 v 0 01975 0 9276 09919 60791 5584 12327 1 3037 14397 I S708 1 6992 18?% 19507 2 0146 2 1977 2 3200 6467 01) h 44 9 S2 1204 7 1231 2 1267 0 299 1 1329 1 1357 7 1412 7 1466 6 IS20 3 1574 4 1629 I 1684 4 !!40 3 17969 s 0 6490 1 4639 14921 1 5284 5595 1 5811 16123 1 65/8 1 6990 11J11 11730 1 8069 18J93 1 8702 1 8998 Sh 8893 78 93 28 93 7893 22893 3?893 47893 52893 62893 728 93 828 93 928 93 1028 93 f 529 e 0 0l982 0 8914 0 9466 1 032) 3094 1816 ! ?504 1 3819 150a5 i s373 17547 1 8746 1 9940 2 l175 2 2302 6411.071 h 45418 1204 S 1228 3 1264 8 297 4 327 7 13% $ 1411 8 1465 9 1519 7 ISP) 9 1678 7 1684 0 1740 0 1794 i 6 0 6540 1 4601 14653 i S223 . $539 i5818 1 6072 1 6530 16943 1 1325 11684 4 8024 I8348 1 8657 l 8954 Sh 24 99 74 99 24 99 74 99 224 99 324 99 424 99 524 99 624 99 724 99 824 99 924 99 1024 99 Set e 0 01990 0 4577 0 9045 0 9884 0640 1342 1 7010 1 3284 14508 1 5704 1 6880 18042 1 9193 20336 2 1471 1475.01) h 458 1[ 1204 4 1225 3 1262 5 295 7 326 3 1355 A 1410 9 I A651 1519 l 1573 4 1678 2 1683 6 1739 7 17964 s 0.6581 14565 14186 1.5164 uS485 S767 16025 16483 1 6897 1 7280 17640 1 1981 18305 1 8615 1 8911 . Sh 2116 7116 121 16 7116 221 is 321 16 42l16 52116 62116 721 14 826 16 921 16 IS21 15 568 e 9 01998 0 8264 0 8653 0 9479 0717 i o902 1 1552 ! ??87 1 3972 15179 1 6266 1 7388 1 8500 19603 2 0699 6478 84) h 46314 12082 1222 2 1260 3 293 9 .324 9 IJM 2 1410 0 1464 4 1518 6 1572 9 1627 8 1683 3 1739 4 1796 i s 0 6634 14529 84720 1 5106 543I i5717 1.5975 1 6438 4 6853 1 7237 1 7598 1 7939 1 8263 18573 1 8870 $h 1743 6743 104) 't' 43 flF41 31743 41743 51743 61743 71743 81743 91743 101743 388 e 0 07006 0 7971 11087 0 9100 0 9824 0492 t il?S 1 2324 1 3473 14593 i n93 16 40 1 78 % 1 8921 1 9980 14 42.571 h 46147 1203 9 in91 1258 0 1292 1 323 4 1353 0 1409 2 1463 7 1518 0 1572 4 1627 4 1682 9 1739 1 17959 s 0 6679 I 4495 14654 1 5049 1.5380 5668 1.5929 1 6394 168tl 11196 1 7556 I 1898 1 8223 1 8533 1 8831 34 1380 6380 11380 43 80 3180 31300 41380 51380 61380 113 80 813 80 913 80 1013 80 198 + 0 0201) 6 7697 0 7944 0 8746 0 9456 0109 10776 l 1892 1 3008 14093 I S160 16711 1 7252 1 8784 19W9 4468 107 4 47170 1203 7 4215 9 1255 6 1290 3 122 0 1351 8 1408 3 1463 0 1517 4 1571 9 1477 0 1682 6 1738 8 17956 s 0 612J 8 4461 1 4590 14993 1.5329 5621 1 5884 16J51 1 6769 4 1135 1 7517 1 7859 1 8184 1 8494 1 8792 Sh 9 il 55 Il los il 155 11 20511 305 11 405 11 SOS 11 60% 11 705 !! 80511 905 Il 1005 11 850 v 0 07032 0 7084 0 7173 0 7954 0 8634 0 9254 0 9835 1 0929 11%9 1 7979 139f 9 14444 1 5909 l6E4 178 3 pg4 891 h 44189 !?02 8 1207 6 1249 6 1785 7 1318 3 1348 7 1406 0 V612 1515 9 1570 7 16?S9 1688 6 1738 0 1794 9 8 l6828 14341 1 4430 1 4858 15207 3 5507 1 5775 1 6249 I 667i I 7059 11422 1 7765 1 8092 1 8403 1 8701 Sh 46 92 96 92 14692 196 92 2Y6 92 396 92 496 92 59692 696 97 79692 89692 9%92 188 e 0 02050 0 6558 0 7771 0 7978 08520 0 9072 1 0102 1 1078 12023 12W8 1 3858 1 4757 1 %47 1 6530 603 CSI h 49160 1701 8 1243 4 1281 0 1314 6 1345 6 1403 7 1459 4 1514 4 1569 4 1624 8 1680 7 1737 2 1794 3 s 06928 1 4304 4 4126 1 5090 1 5399 1 % 73 16 L54 16540 1 6910 1 7335 11619 1 8006 1 4318 8 8617 Sh 39 16 89 16 13916 189 16 28916 389 16 489 I6 58916 68916 789 16 88916 989 16 758 e 0 02069 0 6095 0 6676 0 7313 0 788{ 0 8A09 0 9386 10306 l 1195 ! ?063 1 2916 13759 14597 1 5419 01084) 4 500 89 1200 7 1236 9 1776 1 1310 i 1342 5 1401 5 14376 1512 9 l%82 16218 1679 8 17 % 4 17936 s 0 7022 1 4232 34594 14977 1.5296 15577 1 6065 1 6494 16486 11252 1 7598 1 1926 I 82JS 1 8538 Sh 31 79 81 79 131 79 181 79 281 ft 181 79 481 79 581 79 681 79 781 79 881 79 981 79 868 v 6 07087 0 5640 0 6151 06774 0 7373 0 7878 08759 0 9631 10410 l 1781 1 7093 17885 13669 1 4446 1518 ?!) h 509 S t II99 4 1230 1 1271 1 1306 8 1339 3 1399 1 1855 8 161) 4 1%69 1622 7 1678 9 1735 7 170 9 s 0 7111 1 4163 14472 14869 15198 1 6444 1 5980 1 6413 16807 11175 1 7522 1 1851 1 8164 1 8464 3 Sh 24 76 74 76 124 76 174 76 274 76 374 76 474 76 574 76 614 76 774 76 874 76 974 76 I 818 v 0 02105 0 5330 0 %83 0 6296 0 6829 0 7315 0 8205 0 90.34 0 9830 1 0606 1 1366 1 7115 1 2855 1 3578 l 1525 241 h 51840 1198 0 1223 0 1265 9 1302 8 1336 0 1396 8 149 0 15l0 0 1%57 1621 6 1678 0 1734 9 1797 3 S 0 7117 1 4096 14347 14763 1 5102 15396 1 5899 I 6336 16733 1 7402 1 7450 1 7780 1 8094 1 8395 i Sh 18 05 68 05 118 05 16P 05 268 05 368 05 46805 568 05 668 05 768 05 868 05 968 05 488 s 0 07123 0 5009 0 5763 05869 06348 0 6858 0 1713 0 8504 09262 09998 10720 1 1430 1 2131 1 2825 t 0 31 951 h 576 70 11 % 4 1215 5 1260 6 1798 6 133? 7 1394 4 1452 2 1508 5 1%44 1620 6 1677 ! 1734 1 17616 5 0 7279 I 4032 3 4223 1 4659 I 5010 1 5311 1 5822 1 6243 I6%2 1 1033 1 7382 11713 18028 I 8329 Sh a superheat. F h = enthalpy. Blu per Ib V = specific volume, cu il per Ib s = entr0py, Blu pet F per Ib l 1 B-6

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Iem0) Walef $leem - hmograture - De8'een f sheenheit tbl$g in $41 Sal 550 880 450 146 250 Set 650 ter 1000 1109 1200 1300 1800 1500 Sh -' 18 61 El st 11141 16161 211 41 26141 311 61 361 61 461 61 %Ill 66t li 761 61 861 61 961 61 918 ~ ~ v 0 02141 ' 04721' 04883 0 6485 0 5993 0 6449 0 6871 0 7272 0 76 % 0 8030 0 8753 0 94 % 1 0142 1 0817 1 1484 1 2143 63839) 6 534 74 li9e 7 120s 6 12 % i 1794 4 1329 3 iMI6 1397 0 1421 5 1450 3 IS07 0 1%32 1619 6 1676 2 1733 3 17910 s OJJS8. lJS70 14098 14%7 14921 1 6228 1.5$00 1 5744, 1.5972 4.6193 1 6595 1.6967 1 2317 11649 13965 1 8267 Sh $42 5542 ' 10542 l$5 42 20S 42 2 % 42 30542 35$ 42 4 % 42 555 42 65542 755 42 8H 42 95542 1988 v 0 02159 ' 0 4460 045% 0 5137 ' 0 % 36 06080 0 6489 06875 0 7245 0 7603 0 8295 00%6 0 9672 1 0266 1 0901 1 1529 ($44 581 h $425$ 1192 9 1899 3 1249 3 1290 1 132S 9 1358 7. 1389 6 1419 4 4448 5 1605 4 1561 9 1618 4 16753 1732 5. 1790 3 t 03434 13910 13973 1 4457 ' 1 4833 2 1 $149 I 6476 i H77 I 5908 1 5426 4 6530 1 6905 112% 8 7589 13905 IR07 $h 4947 9947 14947 19947 24947 29947 34947 44947 54947 64947 74947 64947 949 47 1958 e 0 02177 0 4722 0 4821 0 5312 05745 0 6142 0 6515 0 6872 0 7216 0 7881 0 0524 0 9151 09767 1 0373 1 0973 6 50 531 h 55015 !!91 0 1243 4 1285 7 1322 4 13 % 8 1387 2 1417 3 1446 6 1503 9 IMOF 1617 4 1674 4 1731 8 - 1789 6 s 0J507 1 3851 14358 14748 1 5072 1 $354 1 % 04 1 5842 1 6062 46469 1 6845 4 ?!97 1 1531 1 1848 8 8151 . 5h 4372 93 72 18372 193 72. 243 72 29372 34372 443 72 54372 643 72 74372 841 72 943 72 lies v. 0 02195 0 4006 0 4531 0 5017 05440 0 5826 0 6188 0 6533 0 686S 0 7505 0 8121 08723 0 9313 0 9894 1 0468 6$6 281 h 557 % 1189 1 1237 3 ' 1781 2 1318 8 1352 9 1384 7 141S 2 1444 7 1502 4 ' 1559 4 1616 3 1673 5 1731 0 1789 0 s 0 1578 1 3794 - 14259 I and. I 4996 4 S284 i % 42 15779 I 6000 1 6410 1 6787 1 7141 l 7475 1 1793 i 8097 Sh 39 18 8918 139 18 ' 109 18 239 18 289 18 339 18 43918 ' $3918 63918 739 18 839 18 139 18 liss e 0 02214 0 3807 04263 04746 0 5162 0 % 38 0 6889 0 6223 06544 0 7161 0 7754 0 1332 0 8899 0 9456 1 0007 6 61 821 h 564 78 1187 0 8230 9 Q16 6 1315 2 1349 9 1382 2 1413 0 1442 8 IS00 9 1%81 1615 2 1672 6 1730 2 17883 s 07647 1.3738 = 14460 14582 14923 1 5216 1 5478 15717 1 594I I 6353 1 6732 1 7087 1 7422 11741 1 8045 32 81 82 Il 132 81 187 81 232II 282 81 332 81 43281 $12 81 632 81 732 81 832 Si : 932 81 1280 ' e 0 0??)2 0 3674 0 4016 04497 04905 0 5273 0 5615 0 6939 0 6250 06845 0 7418 0 7974 0 8519 0 90 % ' 0 9584 . t%1191 h Sil 85 1184 8 1224 2 1771 8 1111 S 1346 9 1379 7 1410 8. 3440 9 1499 4 t%69 1614 2 1671 4 1729 4 17876 s 01714 13683 - 1 4061 14508 14854 1 5150 1 5415 1 5658 1.5883 1 6298 I H79 1 7035 1 7371 1 7694 1 7996 Sh 2258 72 58 12258 17258 222 58 27258 322 $4 422 58 52258 622 58 ' 122 58 822 58 922 58 13se 00??69 032997 OJ570 0 4052 0 4451 0 4804 0 S129 0 5436 0 5729 0 6287 0 6872 0 7341 0780 0 834$ 0 88 % g577 421 4 58158 1180 2 1209 9 1261 9 1303 9 1340 8 1374 6 1406 4 1437 l 14 % 3 1554 3 1612 0 1%98 1727 9 1786 3 s 0 1843 1 3577 4.3860 14340 14 lit I $072 1 $296 i M44 1 5713 1 6194 - 1 4578 1 6937 63275 1 2S96 1 7902 Sh 1293 6293 112 9) 167 93 217 93 26793 312 93 41293 $1293 61793. 71793 817 9) 917 93 1488 - e 0 07307 0 3018 O M?6 0 3667 0 4059 0 4400 04712 0 5004 0 5782 0 $809 0 6311 0 6798 0 7212 0 7737 0 8195 g47p3 h 598 83. Il15 3 1l94 1 1251 4 12 % i 1334 5 1369 3 1402 0 1433 2 1493 2 1%18 1609 9 L668 0 1726 3 1785 0 s 07966 1 3474 1.3652 14181 14515 14900 1.5182 8 5436 1 % 70 1 6094 6 6484 1 6845 13145 11508 1 7815 Sh 380 5380 103 80 15! 80 20310 253 80 30380 40180 603 10' 603 80 70380 00380 90340 1580 v 0 02346 02772 02870 0 3378 0 3767 0 4049 04350 0 4629 04894 0 1394 O S869 06327 0 6773 0 7210 0 1639 - 15 % 201 h 611 68 1870 1 1876 3 1240 2 1787 9 1328 0 1364 0 1397 4 1429 2 1490 l 1549 2 1607 7 1666 2 1724 8 1783 7 - s-0 8085 1.3373 3 3431 1.4022 ' 1 4443 14782 1 5073 1 5333 1 5572 1 6004 1 6395 1 6759 13101 1 3425 11734 ' Sh 4513 9; 13 14513 195 13 24513 29513 395 15 49513 594 13 695 11 79513 89413 1888 e 0 02387 0 7555 0 3076 0 3415 0 374) 04032 04301 04%S 0 5031 0 5482 0 5915 0 6336 0 6748 0 7153 504 $1) h 674 20 1164 5 I??B 3 1279 4 1321 4 1358 5 1392 8 1475 2 1486 9 1$46 6 1605 6 1664 3 1723 2 17823 5 0 8199 1 3274 1 3861 14312 14%7 14%8 1 5235 1 5478 1 5916 ) 6312 1 6678 1 7072 8134/. I 7657 Sh 3687 8A 87 13687 184 87 2 % 87 28687 386 87 48617 68687 68687 78687 846 87 1788 e 00*428 D7%I 0 7754 0 3147 0 3448 0 17%) 04011 047 % C 4711 06:40 0 % 52 0 5951 0 6341 0 6718 5 13 131 n 6M 45 1158 6 1215 3 1770 5 1314 6 139 9 1383 1 1471 2 1483 8 1$44 0 1603 4 1667 5 1721 7 178I O 5-0 8309 1 3176 1 3697 1 4183 14%5 l4867 l $140 8 5388 1 6833 1 6232 i H01 1 6947 1 7214 1 7585 Sh 74 98 78 88 174 98 17A 98 22898 27898 378 98 478 98 $1898 678 98 778 98 478 98 1888 - e 0 0?472 0 7186 0 7505 0 7906 0 1773 0 3s00 0 3752 0 3988 0 4476 04816 05??9 0 % 09 0 4980 0 6343 1628 021 4 64849 4157 3 1201 2 1261 1 13074 1347 2 1383 3 1417 1 1480 6 1541 4 1601 2 1660 7 1720 1 17797 6 08417 1 3079 ' 1 3526 1 4054 1 4446 14768 i Sost I $302 1 6753 1 61 % 1 6528 1 6876 1 7204 1 7516 $h. 2144 78 44 12144 17144 27144 271 44 37144 471 44 571 44 67144 fil 44 til 44 1988 e 0 07517 ' 070?8 0 7774 076A 7 0 3004 0 3275 0 % 21 0 3749 04171 04565 04940 0 5103 0 % 56 0 6002 1628 % 7 h MG 36 ' 1145 6 1185 7 1251 3 1300 7 1341 4 1378 4 1411 9 14774 1088 1599 l 16 % 8 1718 6 17784 8 0 8522 1 2981 13346 13975 14338 14612 34%0 1 6219 1 % 77 16084 1 6458 1 6808 8 7138 174Si Sh 14 70 64 20 114 20 164 20 214 20 264 20 364 20 au 20 % 4 20 % 4 20. 764 20 84 70 7888 v 0 02%$- 01 AA3 0 7056 0 7488 07 Rot 0 1072 0 3312 0 3534 0 3942 0 4370 04680 0 $027 05M5 0%95 (635 801 4 672 11 1117 3 1568 3 1240 9 129? 6 133% 4 1373 $ 1804 7 1474 I IS36 2 15 % 9 16570 1717 0 ' 1771 I t 0 8625 1 2881 12M4 13794 1 4231 14578 14874 1 5138 1 %C3 1 6014 1 6391 16743 1 7075 17389 Sh 7 74 9 24 10724 19 74 20724 2U 24 30 74 45724 $U 24 lu 24 757 24 IU 74 2188 e 0 07615 0 1750 01247 07304 0 7t?4 0 7AA8 0 3173 0 4119 0 1734 04099 0 4445 04778 0 3101 0 5418 $42141 h 68379 Illn 5 1144 5 17?9 8 1744 9 13?9 3 1%A4 1404 4 1470 9 l$316 1%47 16 % 2 171$ 4 177$ 7 s 0 8727 1 2780 1 294; 43MI 1417% l 4486 14790 1 5060 1 5532 15948 16327 1 H81 1 1014 1 7330 ' Sh % %% IP H IM H 200 % 750 % 3% % 4W% 5M % 4W M Pin % gwn 2288 e 0 07669 O l8N 0 16'6 07134 0 ?458 07770 0?%0 0 1168 03s4% 0 1897 04731 04%I 04%7 0 51 % f649 4Si 4 69546 18'2 7 11?) 9 1218 0 1776 8 13231 130 3 IJ00 0 18U 6 1530 9 IWS 1653 3 17139 1774 4 5 0 8828 1 2676 1 269I I 3523 14070 14196. I e708 I 4984 1 5463 1 6883 1 6266 1 6622 1 69 % L 7273 'Sh 44 11 94 11 145ll 144 11 244 11 344 11 444 11 544 11 644 11 744 11 844 11 2788 e 0 07727 03513 0 8975 07105 07%4 07?93 0 ?999 0 3372 0 1714 040 % 04ua 04u) 04333 16 % 8 98 h 70718 1111 2 179% ) 179 4 lii6 7 11%A I lii% 7 leM 2 IU41 1%0l let% 1717 3 17711 t 0 8979 12%9 1 1381 11sia i4jos 498 14910 1SM7 i $821 16707 16%g I 6101 l 7219 Sh e-Super heat. I h = enthalpy. Blu per lt) w m spetillC volume, CU fl per lb $

• fntropy, Stu per R pe7 lb I'

B -7 .,__,l

Table 3. Supe 7 heated Slesm-Continued Abs Press Lbl30 ln $81 Sal 14*04'8ture - Devees F4 hrenheil s ($81. Iemp) Water - $leem fit 1$6 888 ' $$6 000 950 1000 1950 litt 1150 1290 8100 1800 1500 l Sh 3789 4789 13789 18789 23789 28789 33789 38789 43i39 48789 53789 63789 737 89 83789 2480 ' e 8 02790 0 1408 01824 0 2164 0 7424 02648 0 2850 03037 0 3214 03382 03$45 03703 03856 04tM 04443 0 4724 l%2nD h 71895 1103 7 1191 6 1259 7 1310 1 IM28 1391 { 1426 9 1460 9 14937 19256 lM70 1588 1 1649 6 1710 8 1771 8 8 9 9031 12460 IJ232 8 3408 14217 14549 1483i 7 5095 1.5332 15$53 1 5761 ' 1 5959 18149 1 6509 1 6847 1 7167 Sh 3189 81 89 131 89 18189 231 89 281 89 33189 381 89 431 89. 481 89 531 89 63189 13189. 83189 25M - e 0 02059 0 1307 0 1681 0 2032 0 2293 0 7514 0 7712 0 2896 03068 0 3232 0 3390 0 3s43 0 3692 0 3980 04?st edut l%81D .h 731 71 1093 3 1176 7 12$0 6 1303 4 13474 1386 7 1423 1 14575 1490 7 1522 9 1554 6 1545 9 16478 1709 2 1770 4 s 0 9139 12345 4 3076 1.3701 14129 1 4472 14766 1.5029 1.5269 1 54.2 1 5703 1.5903 1.6094 1 64 % 16796 1 7116 Sh 2409 76 09 126 09 176 09 ??6 09 276 09 325 09 37609 426 09 476 09 526 09 626 09 726 09 826 09 2400 v 0 02938 0 1211 0 l$44 0 1909 0 2171 02390 0 2585 0276S 0 2933 0 3093 03247 0 3395 03540 0 3819 04088 0 4350 1673 311 h. 74447 1082 0 liso 2 1241 1 12 % 5 1341 9 1382 1 1419 2 1454 1 1487 7 1520 2. IM2 2 1583 7 1646 0 1707 7 1769 i s 09247 1222) 1.2908 1 3592 14042 14395 1 4696 14964 1 5208, 1 5434 1 5646 1 5848 1 6040 1.6405 16746 1 7068 Sh 2047 7041 12047 17047 22047 27047 32047 37047 42047 47047 52047 620 47 720 47 820 47 218e v 0 03029 01119 0 1411 0 1794 0 2058 0 2275 0 7468 02ue 0 ?809 07%5 0 3114 0 3769 0 3399 0 3670 0 3931 0 4184 4479 537 h' 757 34 1969 7 1147 0 1231 1 1789 6 1316 3 1377 6 1416 2 1450 7 1484 6 till 5 IS49 8 IS81 5, 1644 1 1706 1 17679 s 0 9356 1 2097 IJ727 8.3481 139$4.14319 14628 64900 15148 1 5376 1 5598 3 5794 IS988 1 6355 1 6697 1.7021 Sh - 1504 65 04 115 04 165 04 215 04 26504 315 04 36504 415 04 465 04 515 04 615 04 715 04 - 119 08 ' 2000 v 0 03134, 0 1030. 0 1278 01685 0 1957 02168 0 2358 0 253 L 0 2693 02445 0 2998 0 3132 0 3268 0 3532 0 3785 0 40t3 1664 961-h 770 69 1055 8 ' !!21 2 1220 6 12822 1330 7 1372 8 1418 2 14472 1481 6 1514 8 1547 3 1579 3 1642 2 1704 5 1766 5 8 0 9464 1.1958 12527 83368 43867 1 4245 14%) 14838 15089 3 5321 1 5537 3.5742 1.5938 1 006 1 6651 1 6475 Sh 9 78 69 78 109 78 159 78 209 78 259 70 30978 359 78 409 78 45978 509 78 609 78 709 78 809 18 2909 e. 0 03262. 00942 01138 0 1581 01853 0 2068 0 ??$6 07427 0 2586 0 2734 0 2877 0 3014 0 3147

• 0 3403 03649 0 3887 i

1690 22) h 18513 1039 8 609S 3 1209 6 1274 7 13?4 9 1368 0 14072 1443 7 1478 5 1617 1 1544 9 1577 0 ' L640 4. 8703 0 17657 1 s 0 9548 1 1803 12283 1.3251 1 3780 14til ! 4494 I4177 I 5032 1 5266 8 6485' 1 5692 1 5889 3 62)9 I 6605 1 6931 Sh 4 67 54 67 10467 154 67 204 67 2 467 30487 35447 40447 45447 50467 604 67 70467 80467 3094 e ' 0 03428 0 08 % 009A2 hl483 01759 0 1975 0 7168 07179 074a4 0 7610 0 7770 0 7904 0 1013 0 3?82 0 3472 OW 1695 331 h 80189 1070 3 1060 $ !!97 9 1767 0 1319 0 1161 7 14011 1440 ? 14is 4 1509 4 1547 4 1574 8 1618 6 1796 4 11614 s 0 9128 8 1619 88%6 3 3131 1 % 97 14097 1 4479 14717 14976 16213 ' 1 $434 1 5647 I 5641 1 6714 36%I 16A44 $h 4972 99 77 149 ?? 199 72 24972 299 72 34972 399 72 - 449 72 499 72 599 ?? 699 12 799 72 1 9100 v 0 03681 00745 OlM9 0 8671 08887 0 2071 02237 02390 0 2533 0 2670 02800 02927 0 3170 0 3403 O M21 1700 28) h 82397 993 3 1185 4 1259 1 1313 0 1358 4 1399 0 1436 7 14723 1506 6 1539 9 1572 6 1636 7 1699 8 1762 6 1 s 0 9914 Il37J 13007 1 3604 14024 14364 14658 14920 1 5161 1.5384 13594 1.5794 161b9 14618 1 6847 Sh 44 92 94 92 144 92 194 92 244 92 294 92 344 92 394 92 444 92 49412 594 92 694 92 794 9' 3788 e 0 04472 00%6 01300 0 !$88 0 1894 01987 071$1 0 2308 07442 02$16 0 2704 0 2877 03065 03291 O M:0 170$ 08) h 875 54 9314 1177 3 1250 9 130W 1353 4 1394 9 1433 L I469 2 1503 8 15374 1570 3 1634 8 1698 3 17612 s. 1 0351 1 0832 1 2817 13515 1 3951 14300 1 4600 14864 1 5110 153M l5547 15749 1 6126 1 6477 168M Sh 3364 0 1713 0 1510 0 1727 0 1908 0 20?0 0 ??ll 0 7357 0 2488 0 2613 0 2734 : 0 2964 0 3181 0Wo h ll?$ 2 12421 1300 7 13484 1390 7 1429 5 1466 1 15010 1534 9 1588 1 1029 1696 7 1759 9 s 1 2142 1 3425 1 3419 I 4237 1 4542 3 4813 i 50$9 3 5287 1 550) 1 5704 4 6084 5 6436 1 6747 3400 v 0 1879 0lan 01653 01M4 0 1944 0 7140 0 ???6 0 7405 0 2528 0 7646 0 2872 0 3088 07?*6 h 11432 1731 7 8294 3 13414 83864 1425 9 1462 9 1498 3 1532 4 15658 16m ]B0% 1631 1 69$ 1 17H 5 s 1 2600 1 3334 1 3807 1 4174 1 4486 1 4761 1 5010 1 5240 1.64 % I % 60 1 6728 Sh 3540 s 0 1048 8 i364 0 l%83 0 1764 019?? 0 7066 0 2200 0 2376 0 7447 0 2563 0 2784 0 ?**5 fi 3188 h 18278 W46 12878 13382 1382 2 1422 7 14$9 7 1495 5 1529 9 !%36 1629 2 16936 179 2 s 1.2450 8 3242 1 3734 1 4112 14430 1 4109 I 49 4 i Site ! $412 I 6618 1 6002 16J58 16691 1sas 0 0866 O l?% 0 1517 0 1647 0 3854 0 19 % 0 2178 0 2752 0 7371 0 2485 0 2702 0 2908 0 3104 h 1108 6 1215 3 1281 2 1333 0 13779 1418 6 84 % 5 1492 6 15274 1%l3 16273 1692 0 17ts 9 s i 2281 1 3148 1 3662 140$0 1 4374 1 4658 1 4914 1 5149 I 5369 1 5576 15962. I U20 1 6654 Sh 3480 v 0 0799 0 1169 0 1395 0 1574 0 1729 0 1868 0 19 % 0 2116 0 7231 0 7340 0 2549 0 7746 0 2936 h 1064 2 8199 5 17676 13?? 4 13696 1411 2 1850 1 1487 0 15??4 1%68 16236 1688 9 17632 s 1 1888 3 29SS 1 3517 3 3928 1 4265 14$$8 4 4821 1 5061 4 5284 1.b495 1 5886 1 6247 I6%4 4eet 0 0631 0 1052 Olm 014A3 O l416 0 1752 O lA77 0 1894 0 710$ 0 7780 0 ?41l 0 n01 0 7781 h 10074 1174 3 th34 13:16 1360 2 14016 14436 1481 3 15173 in?? i6is t leas t 17sa s s i 13 % i 2754 1 3375 l J807 I 4168 I 4461 1 4730 1 4976 1 5203 1 5417 1 $812 1 6171 i H16 47tt 0 0a98 0 0*45 0 1183 0 1367 0 1513 0 1447 0 1769 0 1883 0 1991 0 ?0*3 0 ??87 0 ?470 0 445 h twl 1151 6 1738 6 130n 4 Inl2 1396 0 1078 1455 tilf f 15616 16:6 B 1687 6 I PU S s 1 0905 1 2644 1 3223 I J686 14053 1 4366 4 4642 3 4893 1 5124 1 $J48 I 1742 1 6109 I 64$2 4484 e 0 0471 0 0846 0 1040 0 1770 0 14?0 01 9 01671 0 1782 0 1887 0 1886 0 7t ?4 0 7351 0 2$19 h 909 % 11773 I??) 3 1289 0 13470 1348 J I4604 1469 7 1507 1 15430 1612 3 1679 4 l'45 1 s 10$56 1 2325 1 3073 13%6 1 3949 I 4272 1 45 % 1 4812 4 $048 8 $268 l % 73 I 6044 1 6391 Sh = Superheat. F h = enthalpy. Blu per Ib v = specibc volume, cu it per Ib s = entF0py. Btu per R per Ib 0-8

l l Table 3. Superheated Steam-Continued $8 fg $,i 3,1 temperature - 0ereel f ahrenheit (Sat. Tem 01 Water $leam 250 800 050 000 050 1000 1050 1100 1150 1200 1250 1300 1800 1500 s 4888 v 0 0380 0 0741 0 1005 01186 OLDS 0 1465 0 1582 01691 0 1792 0 1889 0 1987 0 7071 0 ??42 0 2404 h 883 8 1100 0 12013 1277 2 1332 6 1380 5 1473 7 1463 9 1501 9 1538 4 1571 4 1608 5 1676 3 L742 7 s 1 0331 1 2084 IJ922 1.3446 1 3647 1 4181 1 4477 1 4734 1 4974 1.5197 1 5407 1 % 07 1 5982 1 6330 Sh 4888 e 0 0355 0 0665 00927 0 1109 0 1757 0 1385 0 1500 0 1606 0 1706 0 1800 0 1890 01977 0 ?i42 0 ??99 h 866 9 1071 2 1190 7 1265 2 13231 1372 6 14170 1458 0 1496 7 1533 8 l%97 1604 7 16731 17400 s 1 0140 L1835 1 2768 1 3327 1 3745 1 4090 1 4390 14657 1 4301 1 5128 1.5341 1 5543 1 5926 1 6212 34 5888 v 0 0338 0 0591 0 0855 0 1038 0 1185 0 1312 0 1475 0 1579 0 1676 0 1718 0 l806 0 1890 0 2050 0 2703 h 854 9 10429 1173 6 1252 9 l*l3 5 1364 4 1410 7 1452 6 14915 1529 1 15r6 5 1600 9 16700 17374 s 1 0010 1.159J 1.2612 1.3207 1 3645 4 4001 l 4309 1 4582 3 4831 1.5061 1.5477 1 5441 1.5363 1 6216 th 5288 e 0 03?6 0 0531 0 0789 0 0973 0 1119 0 1744 0 13 % 0 3458 0 1553 0 1642 0 1728 0 1810 0 1466 0 7114 h 445 8 1016 9 11 % 0 1240 4 13037 1356 6 14034 14462 1486 3 35245 15663 15972 1%68 1734 7 8 0 9985 l 1370 1 2455 l 3088 1 3545 1 3914 14229 i 4509 4 4762 3 4995 1 5214 1 5420 1 5806 1 6163 Sh A400 v 0 0317 0 0483 0 0778 0 0912 0 1058 0 1187 0 !?97 0 1392 0 1485 0 1572 0 1656 0 1736 0 8A88 02031 h 838 5 994 3 1138 ! 1227 7 12937 13484 1396 5 1440 3 leal 1 1519 8 15571 15934 1663 7 1737 1 0 9915 I il75 1.2296 1 2969 1 3446 1.3827 1 4151 4 4437 1 4694 14931 1 5153 1 5362 1 5750 1.6109 Sh 5488 v 0 0309 0 0447 0 0617 0 0A56 0 1001 0 1174 0 1732 0 1331 0 1422 0 1508 0 1589 0 1667 0 1815 0 1954 h 832 4 975 0 1819 9 1214 8 !?83 7 13407 1389 6 1434 3 1475 9 1515 2 1557 9 1589 6 1660 5 17295 s 0 9855 1.3008 1 2137 11850 1 3348 1.3742 3 4075 1 4366 1 4628 14469 3 5093 1 $304 1 % 97 1 6058 Sh 8888 e 0 0303 0 0419 O rin?? 0 0805 0 0449 01070 01177 0 8774 0 1343 0 1447 0197 O I A01 0 1747 O IRA) i h 877 9 954 4 1101 8 1701 8 1771 6 8317 0 1347 6 147A 3 1470 6 1510 5 1544 7 15458 16U 4 177s. n s 0 9803 1.0867 3 1981 1 2732 1 3250 1.3658 1 3999 8 4217 14%4 1 4808 3 50J5 1 5248 1 M44 1 6008 Sh 8888 e 0 0298 0 0397 0 057 0 0757 0 0900 0 1070 0 It?6 0 1221 0 1309 0 1398 0 1469 0 1544 0 1684 0 181? h 822 9 9451 1084 6 1188 8 12834 1323 6 13757 1427 3 14654 1505 9 1544 6 15820 1654 2 IJa ? s 0 1758 1 0746 ! !8L 1 2615 1.3154 1 3574 1.3925 1 4229 1 4500 1 4748 1 4978 1.5194 1.559J 1.5963 bh 8588 e 0 0287 0 0358 00J95 0 0655 0 079) 0 0909 0 1012 0 1104 0 1188 O !266 0 1340 0 1411 0 1544 0 1669 h 813 9 919 5 1046 7 IIM 3 12378 13^? ? 1358 1 1407 3 1452 2 1494 2 1534 1 157? S 16464 17 16 s 0 % 61 1 0515 1 1506 1.2328 1 7917 12.Q l.3743 1 4064 1 4347 1 4604 1 4841 1 5062 1 54 ?! 1 5844 $h 1100 v 0 0279 0 0334 0 0d38 O tA '3 0 0701 0 0816 0 0915 0 1004 0 1085 0 1160 0 1231 0 1798 0 1424 0 1542 h 806 9 90t 8 1016 5 1824 9 12126 1281 7 13405 13922 1439 1 1482 6 15237 8563 1 16386 17111 s 0 9582 10J50 1.1243 1.2055 1.2689 1 3171 13%7 1.3904 1 4200 1 4466 1 4710 1 4138 1 5355 I 5735 Sh I580 v 0 0772 0 0318 0 0399 0 0512 0 0r 31 0 0737 0 0833 0 0918 0 0996 0 1068 O ll36 O l?00 0 13?' 014D h 801 3 889 0 992 9 10977 l188 3 1261 0 879 13772 14?6 0 84710 1513 3 15537 1630 8 1704 6 s 0 9514 1 0224 8 1933 1 1818 1 2473 1.2980 1.3357 L 3751 1 4059 I 4335 1 4586 1 4819 4 5245 1 5632 Sh 1888 e 0 0767 00J06 0 0371 0 0465 0 057) 0 0671 0 0767 0 0845 0 0920 0 0989 01054 0 1115 0 1730 0 I338 h 1956 4791 9'44 1074 3 11654 1241 0 1305 5 13672 14:30 1459 6 15031 15445 16231 1698 1 s 09455 1 0122 1 0864 1 1613 1 2271 1 2798 1.3233 1 3603 1.3924 1 4208 14467 1 4705 1 5140 1 P13 Sh lige v 0 0762 0 0?% 0 0350 0 04?9 0 05?2 0 0615 0 0701 0 0780 0 0853 0 0919 0 0982 0 1041 0 1151 0 1254 h 79? ? 871 2 959 8 1054 5 1144 0 17219 1788 5 13475 1400 ? 14482 1492 9 l535 3 1615 4 1691 7 s 0 $402 1 0037 1 0127 1.1437 1 20 &4 1 2627 1 3016 1.3460 1 3793 1 4087 14352 3 4597 8 5040 1 5439 Sh 1800 v 0 0?$8 0 0?88 0 0335 0 0402 0 0483 00%8 0 0649 00??4 00794 0 0058 0 0918 00U5 01081 0 1179 h 789 3 864 7 9A8 0 10376 1125 4 12041 1272 1 1333 0 1387 5 1437 I 148? 9 1526 3 1607 9 1685 3 s 0 9354 0 9964 10613 1 1285 1 1918 12468 1 2926 1 3323 13661 1 3970 14243 1 4497 1 4944 1 5349 84 1588 v 0 0754 0 0*B2 0 01?? 0 03A0 0 0441 O lMS 0 0603 0 0675 0 0742 0 0404 00A47 0 0917 0 1019 01 13 h 7%4 859 7 938 3 10?)4 180A 9 Il8f 7 12 % 6 13:4 9 1315 1 14761 I4711 85171 Irand 16M o n 0 9310 0 9900 1 0516 1 1153 1.1711 1 2320 12785 13191 13546 1 3858 18137 1439? 1 4858 1 5263 34 18988 v 0 0251 00??6 0 0312 0 0362 0 04 ?5 0 0495 00%5 0 0633 0 0697 0 0757 0 08l? 0 0965 0 0953 0 1054 h 7830 854 5 930 7 1011 3 1094 7 !!17 6 17420 13053 13679 1415 1 14534 150A 6 159 :1 1677 8 s 0 9270 0 9842 1 0432 1 1039 1 1638 1 2185 1 2652 1 3065 1 3429 I 3749 1 4035 1 4295 1 4,63 1 5180 54 telse v 0 0?48 0 0271 0 c303 0 0147 0 0404 0 0467 0 0537 Cats 0066 0 0714 0 0768 0 0918 0 0913 01001 h 781 5 850 5 923 4 10010 1081 3 l1519 1278 4 1792 4 135 t l 1404 7 1453 9 1500 0 15858 1666 7 s 0 9732 0 9790 1 0358 1 0939 1 8519 I 2060 1 2529 1 2946 1 3371 1 3644 1 3937 1 4207 I 4617 3 5100 Sh = superheat I h = enthalpy. Btu per Ib v = specific volume, Cu f t per Ib 5 = entropy, Stu per F per Ib B -9

Table 3. Superheated Steam-Continued Abs Press (D/5g in $al Sal I'mperalvse-Detetes f ahrenheil (Sal. lemol W3ter Sleem )$g 300 3$$ 300 g$$ 1000 1958 1100 1t10 1260 1250 1380 1408 1500 11886 e 0 0745 0 0?61 0 0296 0 0335 0 0386 0 0443 0 0503 0 0562 O M70 0 0676 0 0127 0 0 h 779 5 846 9 9175 99? l 1069 9 1646 3 12159 12R02 1319 7 1394 4 1444 6 1491 5 157 s 091% 0 9742 1 0797 i 0858 a 1417 I 1945 1 2414 8 2833 l 3209 l 3544 1 3842 3 4112 11388 e 0 0743 0 0253 00?*0 O r'3?S 0 03/0 00J23 0 0478 0 0534 0 0588 0 0641 0 0691 0 h 7777 8438 912 4 T5 1059 8 1114 9 1204 3 1268 7 1328 8 1384 4 14355 14832 157 8 0 5163 0 9698 1 0732 1 0712 1 1316 1 1840 1 2308 1 2727 1 3107 1 3446 1 3750 12888 e 0 024l 0 0?60 0 0?84 0 03 t ? 0 0357 0 0405 0 0456 0 0508 0 0560 0 0610 0 06 h 776 1 841 0 9079 977 8 1050 9 1124 5 1193 7 1258 0 -1318 5 1374 7 l426 6 1475 1564 9 1648 8 s 0 9131 0 % 57 1 0177 1 0101 1 1729 1 1742 l 2209 L 2627 l 3010 1 3333 1 2662 1.3 t!588 e 0 0738 00?s6 0 0779 0 0309 0 0346 0 0390 0 0437 0 0486 0 0535 0 0583 0 06?9 h 774 7 838 6 903 9 974 9 10431 1l15 2 1184 1 17479 1308 8 13654 1418 0 64612 s 0 9101 0 9618 1 0177 1 0637 I ll$1 1 1653 I til? l 2534 lJ9il I 3264 1 3576 1 3860 1 13888 e 0 0236 0 0753 0 0775 0 0107 0 0134 0 0176 0 0470 0 0464 0 0512 0 0558 00Ml? O 6 771 5 8M3 900 4 %68 1016 7 11% ) 6574 8 1738 5 17M 6 11%6 5 14:19 6 14%9 4 1551 6 16374 s 0 9073 0 9587 1 0040 1 0578 1 1079 8 1571 I 7030 1 7445 !.7438 ,1 3179 8 3494 1 3788 1 4791 1 4741 13388 e 0 0735 0 0256 0 0771 0 0797 0 03?8 0 0364 0 0405 0 0448 0 0492 0 0535 0 0577 0 0 h 772 3 834 4 8172 962 2 1010 0 19991 Il66 3 1729 7 1791 0 1348 l 14015 1451 4 154 s 0 9045 0 9548 1 0037 1 0524 1 1984 I lati i 1948 L.2365 1 2749 l 3098 1 3415 1 370 14888 v 0 0733 0 0748 0 0?67 0 0791 0 0320 0 0354 0 0392 0 0432 0 0414 0 0515 0 0555 0 5 h 771 3 832 6 894 3 958 0 1024 5 8012 3 1558 5 17214 1283 0 13402 1393 8 1444 4 1 4 0 9019 0 9515 0 99 % 10473 1 0953 1 1426 1 1872 12282 1 2671 1.3021 13339 1 363 14588 0 0231 0 0746 0 0764 0 0287 0 0314 00345 0 0380 0 0418 0 0458 0 0496 0 0534 0 0573 0 h 770 4 8J10 8t ? 954 3 1089 6 10842 1151 4 1213 8 1775 4 1332 9 13864 1437 3 1532 6 162 9 0 8994 0 9484 0 9957 1 0426 1 0897 11362 1.1801 1 2208 1 259? 1 2949 1 3266 1 35 158g8 0 0?30 0 0744 0 0261 0 0782 0 0108 0 0337 0 0369 0 0405 0 0443 0 0479 0 0516 0 0 h 7696 879 5 8833 950 9 1015 1 1060 6 1144 9 !?06 8 12681 1326 0 1379 4 143c 3 15 s 0 8970 0 9455 0 9920 1 0382 1 0846 1 1302 1 1735 1 7139 1 2525 1 2880 1 3197 1 34 15588 0 0*78 0 D?d2 0 0758 00;)$ 0 0.10? 0 0379 0 0360 0 0393 0 0429 0 0464 0 04*9 0 0534 0 0603 0 0668 h fu t A?8 7 AA 7 2 9478 let t i 1075 7 11390 170n 3 I?611 13196 13778 1423 6 15104 16 s 08116 0 9417 0 988b I 0340 1 0797 1 I?47 1 1674 1 2013 1 2457 1 2815 1 3131 1 34 Sh = superhnt. F V = SpecifM v0!ume. Cu it per Ib h - enthalpy. Btu per Ib 3 m entropy, Btu per R per Ib B-10 1 1 _-__J

S 9 0 9 i ANSWER KEY i i TER MAS 1

L _EBIN91ELES_QF NUDLEAE_E0HEB_ELABI_9EEBAI19L PAGE 24 IHEBMQDYBAMIES2_HEAI_IBANSEEB_AUD_ELUID_ELQW ANSWERS -- PERRYEl&2 -87/06/01-DANIELS, M. i i ANSWER. 1.01 (1.50) i

a. 812 btu /lb (+ or - 50 btu /lb)

b. 71% (+ or - 2%)-

c. 389 btu /lb

(+ or - 50 btu /lb) (3 required at 0.50 ea) REFERENCE j Mollier Diagram . Steam Tables l Perry Nuclear' Power Plant Thermal Sciences .pp 4-6, 4-7 293003K123 ...(KA'S) ANSWER 1.02 (1.50)

a. Transfer o'f heat from molecule to molecule in a stationary substance

b. Heat transfer between a flowing fluid and a surface c.

Heat transfer between mutually exposed surfaces Also accept heat transfer by electromagnetic radiation REFERENCE

Perry Nuclear Power Plant Thermal Sciences pp 5-2, 5-27, 5-30 293007K101

...(KA'S) ANSWER 1.03 (1.00) 89.64 PSIA (+ OR 1 PSIA) (1.00) REFERENCE Steam tables Perry Nuclear Power Plant Thermal Sciences pp 7-3 293007K106-293003K123 ...(KA'S)

lCiEBIEIELES OF HELEAB_.EQWEB_ELAHI_QEEBAIIQL PAGE' 25 IHERMQDYNAMICS2_ HEAT IRANSFER AND_ELUID FLOW ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. ANSWER '1004' (~c50) TRUE (0.50) REFERENCE 'PerryL Nuclear Powe r l'1 ant Thermal 'Scierices pp 4-3 293008K10'/ ...'( KA ' S ) ' ANSWER- '1.05 (1.00) d (1.00) REFERENCE

Parry' Nuclear Power Plant Thermal Sciences.pp 10-4 293009K106 293009K104

...(KA'S) . ANSWER 1.06 (1.00) d REFERENCE BWR' Academic Series on HTFF pp 6-100

293006K113

...(KA'S) ANSWER 1.07' (1.50) la. The reduction of condensate temperature, by excess condensing capacity..( This prevents saturated conditions at the eye of the condensate pump impeller, preventing pump cavitation.) Also accept, The cooling of the condensate in the condenser below the saturation-temperature ib. To much. condensate depression reduces the plant efficiency. (For each degree the condensate temperature is reduced, one ' btu /lb is given'up and must be added by reactor heat) REFERENCE-Perry Nuclear Power Plant Thermal Sciences pp 6-25 293008K119 ...(KA'S) l l ~ _ _ x- _ _ ---__----____------_--_--_-_.---,)

.1 PRINCIELES_QE_EUQLEAB_EQHEB PLANT OPERAIIQN2 PAGE 26- --IHERMQDXHAMlQS2_HEAI_IBABSEER AND FLUID FLQH ANSWERSL---PERRY 1&2. -87/06/01-DANIELS, M. [ ANSWER 1.08 (1.50)

a. Using a simplified equation CTP = Mfw (hg-hfw)/c1 + constant MW, considering heat losses or gains due to cleanup demineralizers, recire pumps, CRD flow and; fixed losses <as a l

single. fixed quantity.Also ignoring steam moisture and CRD flow

b. Correlating core thermal power to generator output.

c. Core thermal power can be estimated by the power range nuclear instrumentation', assuming the instrumentation has been recently calibrated to a heat balance.

(Any 2 at'O.75 ea) REFERENCE

BWR Academic Series pp 7-49,50,51

.293007K111 ...(KA'SJ ANSWER 1.09 (1 00) b ~ REFERENCE l Hollier Diagram 1 ~ Parry Nuclear Power Plant Thermal sciences pp 3-8 to 3-10 293007K106 ...(KA'S) 1 ' ANSWER 1,10 (2.00) a. 300 bundles 4 or - 25 bundles ) (0.50)

b. The-source is' located to close to the detector.

(0,50)

c. Non-conservative. (0.50)The indication after 150 bundles would 1

indicate.some 500 bundles would be required for criticality. Based on that assumption, more than the critical number of 1 bundles could have been loaded if no other readings were taken. (0.50) I .J

) 1 i ,1 PRINQIELES OF NUCLEAB POWER PLANT OPERATION PAGE-27 2 THERMQDXNAMICS._HEAI._IBANSFER_AND FLUID FLQW ' ANSWERS - 1 PERRY 1&2 -87/06/01-DANIELS,.M. j REFERENCE' BWR Academic series Reactor Theory pp 3-14 292008K105 292008K104 ...(KA*S) ANSWER 1.11 (1.50) a' Gadolinium is a burnable. poison loaded into the core to allow more fuel to be loaded (higher K-excess) without increasing th number of control rods. (0.50)

b. Gadolinium is loaded more heavily.towards the bottom of the core.

(0.50)

c. This distribution provides la power flattening effect, minimizing the need for shallow rods and permits a more optimum exposure shape.

(0.50) REFERENCE-BWR Academic Series Reactor Theory pp 6-16 292007K101 ...(KA'S) ANSWER -1.12 (2.00)

a. dk/k = (-1x10EE-4 dk/k/F) (-110 F)

-dk/k = 110 EE-4

b. (dk/k)1 = 0.99-1/0.99 = -~0.0101 (dk/k)2 = (dk/k)1 + (110EE-4 dk/h)

=.0101 + 110 EE-4 dk/k =9.0 EE-4 dk/k Keff 2 = 1/1-9 EE-4 dk/k Keff 2 = 1.0009. (+ or -.00005)

c. Period = (.0072-9 ee-4)/(0.1)(9 EE-4)

Pe'riod = 70 seconds (+ or - 2 seconds) d.Heatup of the moderator will terminate the power increase due l to the moderator temperature coefficient. i

REFERENCE

'BWR Academic Series heactor Theory pp 4-9 '292004K102 292003M110 .(KA'G) I 1 _o

11_iEBINCIPLE0_DE ND_cLEAB E0 WEB._ELANT._DEEBAII0th PAGF. 20 ^ ~ IUESUONUAMEL_11E61_IBANHEEB_AND._ELUID_EL9E . ANSWERS -- PERRY 1&R -87/06/03-DANIELS, M. NNSWER 1.13 (2 60) 1

a. Doppler,-or fuel temperature (.25) negative (.25)-

b. Void (.25) negative (.25)

c. Moderator temperature (.25) negative (.25) c

'd. Void (.25). positive (.25) e. Moderator temperature-(.25) positive (.25) REFERENCE BWR' Academic Series Reactor Theory pp 4-9,10 292004K114 ...(KA'S). ANSWER 1.14 (2.00) The. reactor was shutdown by 1% dk/k at the time'of peak xenon, therefore ohutdown margin will decrease as xenon decays.-Since the xenon peak is greater thhn 1% dk/h. an inadvertent criticality could occur. REFERENCE-BWR Academic Series heactor Theory pp 6-11 292002K114 ...(KA'G) ANSWER 1.15' (1.50) a (0.50) At low power, the cold water sprayed into the core exit region'has a more sigificant effect on the moderator temperature.(1.00) REFERENCE. RBWR Academic Series Reactor Theory pp 4-38 292004K102 ...(KA'S) (

1.m_EBIHgIELES_QE_SUCLEAR POWEB_ELANI_QEEBAIlO8, PAGE 29 .TBEEdQDYNAMIgh _HE8I_IBAUSEEB_AHD ELUID_ELQW ANSWERS - PERRY 1&2 -87/06/01-DANIELS, M. ANSWER 1.16 (3.00) l a. No significant affect. b. Less rod withdrawal.

c. More rod withdrawal.

d. No significant affect.

e. Less rod withdrawal.

f. More rod withdrawal.

REFERENCE Perry Exam Bank 292008K103 292005K104 ...(KA'S) I

.Y ~ PLANT DKEIGH_lELEING SAFETY AND EMERGEEY SYSTEME-PAGE 30 ' 87/06/01-DANIELS, M. ANSWERS'-- PERRY 1&2 5NSWER 2.01: (1.50)

a. ADS l'ogic in test

)

b. ADS /SRV' logic, or solenoid power lost

c. ADS. trip unit out of file, or power failure

d. ADS trip unit in cal,.or gross failure

e. Activation of inop switch (any 3 0 0.60 ea) 4 W AC W r. fehtVC/r) foWM Jef fcwMMNW1f AMI SACi5AflhM

. REFERENCE 41 /N/!i Vidukt.,&VfusM/ ww1 rat difv es Porry Nuclear Power Plant System Description Manual

Automatic Depressurization System pp 5 218000K604 218000A205 218000K60S 218000K605

...(KA'S) JANSWER 2.02 (1.50)

a. MGIV's close (0.507 i

b. Reactor scram -(-0. 5 0 T-

c. Main Steam Line Drains c3ose

(.O--6tr) ( 6, net Arted #F fig sk,ntf4C V4wH REFERENCE e.;rArgi vc-of jos.e,y, vivi. y+ccown pfam/5 (3 jfrquist// 5 0.sv n.) - i Perry Nuclear.. Power Plant System Descriptions Manual Nuclear Steam Shutoff System pp 6 223002K108 223002K107 223002K102 223002K101 223002A401 ...(KA'S) i

M; y 2. ~ PLANT _ DESIGN INCMID1HQ_SAEEIY_ AHD EdEBGEEY SYSIEMS PAGE: 31 ANSWERS -- PERRY'1&2 -87/06/01-DANIELS, M. _ . F ,e a d .f' , 1 ANSWER 2.03, fl.50) M 9 1m.. Operating the keylock-switch on P601 5

b. Operating the keylock switch on EF*0-7 pdret dowr5e/- MwMM

.c. Placing the pump control switch ~in the Control Room to the ON position N

3. /do//. M,/*M/,-

(/ required at 0. '!0 ea) 2.- o a 7)~ REFERENCE- . Parry-Nuclear Power Plant System Description Manual Standby. Liquid Control-System pp 10 211000K4067 211000A104 ...(KA'S) 1 d ANSWER j2.04 (1.75) F 'I e

a. High containment pressure (0.25) 8.35psig(0.25)(94to9,JQvy)

~ b, High drywell. pressure (0.25) 1.68 psig (0.25) 1 ./ : te. LPCI running (0.25) In ou ration for ten minutes (0.25) of A6c/.<jvnypriott ')16N#4 (orsf) s'iw 7pA,,tdencrr/ (o, >s~.) REFERENCE i Porry Nuclear Power Plant Description Manual ] Residual Heat Removal pp 2 j 205000K104 205000K102 205000K101 ..(KA'S) q 1 L s T. c t t I-I tn 3 ik l l q,.. 4 r.

2 PLANT DESIGN INCLE.ING1 SAFETY AE._EldERGEHCY SYSIEM PAGE 32' ' ANSWERS -- PERRY,1&2 [] -87/06/01-DANIELS M. 4 k{ } t k ) ( ' ~, ,y l ANSWER 2.05 (2.50) '4 (# l a.1 Low Reactor Vessel Water Level (0.25) Level I (0. 25) o,-/ rd /wch/ I a.2.High Dryw> ell Pressure (0.25) 1.68 psig (0.25)' ] 1 b.1TheTeckhtoSuppressionPoolvalve(F012) is c?$ sed' S I b.2 The Suppression pool suction valve (F001) ib open y( ) t' b.3 The LPCS pump,ip, running i l b.4 The LPCS infection valve (F005) opens when r' actor pressure e is less than'577.7 psig.e m v too p wy i" i b.5 The injection check valve (F006) disc indicates open when l LPCS discharge siressure is greater than reacWr pressure. I b.6 Pump flow is proper for the existing pump diLcharge pressure. j r M Ni M v M N w W M W M M f f. (any 4 at 0.25 ma '1 1

c. Yes (0.50) (Required for'either mode of operation) 1 i

REFERENCE 1 Parry Nuclear Power: Plant System Description Manual Low Pressura Core Spray J pp 19,20 1 ) 409001K301 20900g.K7N 209001K114 ...(KA'S) } j. \\% .) ANSWER 2.06 M 1. 50 ) s i .. h \\ (' e

a. Manually returnird the stop valve control switch to the fully

j. closed position' (0.50) \\ v b.Must be. manually r4s%, f tai at the turbine (0.50) { t c.The turbine will cycle on and off between iste?s 2 and.. level 8 Vth f).'50 ) A, c t i 4 ? REFERENCE 4' Perry duelear,$ower Plant System Description Manual W, N!' I

• R2 actor Core Tsolation Cooling p6 12, 15 217000K506

' 217000K202 209LQ2K201 ... ( KA ' S ) + 4 ) n y t p s I p s b l { [N,yL l 1 , i 1 4 j 4,; h ~ g 4

l l

\\' f 4 i ? a f ? y

W< '8,, , /? (.. r 4,

• f ' 2 '.' ' PLANT DESIGN INCLUDING SAEETY AHD_.EMERGEHQY_EYEIEME' PAGE 33 LANSWERS -- PERRY 1A2

-87/06/01-DANIELS, M. L%: i l ANSWER 2.07 (1.00) A hydrogen." getter" is installed'in the plenum at the top of the fuel: rod. (0.50) Reaction.with water or hydrogenous material takes place in the getter rather than on the surface of'the Zircaloy cladding. (0.50) REFERENCE i Parry Nuclear Power Plant System Description Manual ~. Fuel pp-15 l ' 300002K505 ... ( KA' S ) s.., i -8 I ANSWER 2.08 (2.00) Three rows of' vents'ere installed in the drywell wall below the normal i wnter level oi' the suppression pool. (0.50) As drywell pressure increases, the level in the drywell annulus decreases (0.50) causing the ficut row of v6nts to be uncovered, allowing the steam-air mixtur. 1: :.. : ;.s T.. '.

m sc:ont.ainment. vc.: 0 19:.:f the.tupprassion pool where it condenses. (0.50)

Ad 6rywell pressure-increases, the' water level in the annulus continues to i dscreass titil all three rows of vents are uncovered, allowing a maximum l volume of the steam-air mixture to escape and be condensed (0.50) t REFERENCE ' Por'ry NucliearzPower. Plant System Description. Manual l 1 R actor Containment System pp 1 RKTERENCE .Porry Nuclear Power Plan.t System Description Manual - Auto Depressurization. pp 1-4 9 Miin Steam System pp 15 22300lK504 233001K503 ...(KA*S) ~ \\ % ;( i I I 1 k\\ l L 'l ' r 4 u e, v v% f fs 4 L t. $L I i L ,T

ll ,2. ' PLANT DESIGN INCM! DING SAFETY AND EMERGENCY SYSTEMS PAGE 34 ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M.

ANSWER 2.09 (4.00)

a. Auto relief mode, (O W Safety Mode

( 0-G6-) Low Low Setpoint Mode .( 0 - G6 ) ADS Mode (0.25; /4ANupt vuxt-Arr4cok Sworch' (/n y.9 a f e xce)

b. The auto relief mode is activated by high reactor vessel pressure

( 0--SM The safety mode is initiated by high steam pressure at the valve (tr 75) The low low setpoint mode is armed when the first SRV reaches its setpoint (1103 psig). When armed, the two (2) SRV's with setpoints less than 1103 psig will open. Once open, they remain open until the low low reclosure setpoint is reached Hh44) The ADS Laode is initiated by low reactor water level, OR high drywell pressure. (0.25) }4pacp4 e f wirc# 7M:tFN 70 9?/A' [.3M 4 &f Go77 es The auto relief mode prevents over pressurization of the ) c. nuclear system' (^.5&) In the safety mode the valves are set higher than the relief valve setting as a backup in the event the valves fail to open on vessel pressure ft;"J6) The low low setpoint mode prevents the next group of valves from opening thus prolonging valve life t0.50) j The ADS mode acts to reduce reactor pressure to allow low pressure injection systems to flood the core, if the High Pressure Core Spray system is unable to maintain level. /tpup t. -)mpipt t c,seu t-Sc5}<4Bf ft Mfoek HC#*6* W** ( '

• E ts me jawdt-MS#N! W MM0/"M REFERENCE yAtup pypried cA o

4 g g,,yo rg) Parry Nuclear Power Plarft' ystem(De'pjg/scscription Manual L-Y n m A p Auto Depressurization pp 1-4 Mnin Steam System pp 15 239002K108 239002K101 239000K501 218000K106 218000K102 ...(KA'S)

'2. ' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS' PAGE 35 ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. ANSWER 2.10 (2.00) a.1 Loss of Voltage (0.20) 2 Degraded voltage (0.20) b.1 Loss of voltage, activates automatic functions at 75% of rated voltage (0.20) and initiates the following; EH11 (EH12) Stripped Undervoltage Alarm (0.20) Automatic stripping of EH11 (EH12) buses (0.20) Automatic Diesel startup (0.20) ' Inputs to loop circuitry (0.20) b.2 Degraded voltage, activates automatic functions at 95% of rated voltage (0.20) and initiates the following; Initiates Voltage Degradation alarm on bus EH11 (EH12)'after a 16' second time delay. (0.20) If the condition exists for an ADDITIONAL 5 MINUTES the actions for a loss of voltage occur (0.20) . REFERENCE Parry Nuclear Power Plant System Description Manual AC Electrical Systems pp 13,14 262001K402 262001K305 ...(KA'S) ANSWER 2.11 (1.50)

a. Turbine trip at greater than 30% power (0.25) i Turbine Stop Valve closure at greater than 30% power (0.25)

Turbine Control Valve fast closure at greater than 30% power (0.25) l

b. Downshifts both recire pumps (0.25)

c. At end of core life the control rods insert very little negative' reactivity in the fist feet of travel on a scram. The downshift of the recire pumps inserts negative reactivity due to voids (0.50)

REFERENCE Porry Exam Bank l 202001A211 202002K604 202002K605 202001K609 ...(KA'S)

r~w -i 2: " PLANT DESIGN INCLUDING BAFETY AND EMERGENCY SYSTEt2t' PAGE 36-ANSWERS ~~-- PERRYo1&2 '-87/06/01-DANIELS, M. 5 - ANSWER 2.12 (1.00) 4 a.1 Low differential temperature between the bottom head'and the steam dome. (0.25)' 2 Low differential temperature.between the dome and the recire Pump suction (0.25) .3. High differential-temperature between the two recire pump suctions (0.25) 4

b. Prevents starting the recire pumps in fast or low speed (0.25)

REFERENCE Perry Nuclear Power Plant System Description Manual ' Reactor Recirculation System 202002K406 ...(KA'S) LANSWER 2.13 (1.75)

a. No generator lockout

- b. No bus lockout

c. Diesel Generator up'to rated voltage-

d. Voltage upstream of the normal preferred, or alternate preferred supply breaker with the breaker closed.

e. LOCAL / REMOTE switch in REMOTE

f. Synchronizer selector switch selected to either normal or alternate power sources

g. Breaker control switch in CLOSE (7 required at.25 ea)

' REFERENCE Perry Nuclear Power Plant System Description Manual LStandby Diesel Generator System Table R43-3 264000K401 ...(KA'S) u-_ m_____.U.___m_____

L 2 PLANT DESIGN INCLUDING SAFETY AND_ EMERGENCY SYSTEMS PAGE' 37 ? ANSWERS -- PERRY.1&2 -87/06/01-DANIELE, M. 4 L-ANSWER 2.14 (1.50) a..The auction strainer has a 200% capacity mesh. If 50% of the l surface becomes clogged there is still adaquate NPSH for the pump. (0.50) d W / *ll' A M b kely4f efid,t h

• h Y

b. The suction strainer 17 eep enough to' prevent air entrainment-during a LOCA blowdown 0.50) and is clear of the relief valve quenchers, avoiding a hot water suction. (0.50)

REFERENCE-Parry Nuclear Power Plant System Description Manual High Pressure Core Spray pp 5,.6 209002K102 ...(KA'S) 1

[ j ". INSTRUMENTS AND CONTROLS 'PAGE 38 l, ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. .~ ANSWER 3.01 (1'.50) a. By depressing the S23 and S69 pushbuttons on p870 (0.50) b', A' red indicatingflight comes on above the pushbutton, 11 th+. pushbutton has been depressed and a low. vacuum condition exists. (0.50)

c. When vacuum is established / reestablished the bypass is l

aut.omatically reset and the rad indicating light is I extinguished. (0.50) REFERENCE Perry' Nuclear Power Plant System Description Manual Reactor Feedwater System 216000K116 216000A102 ...(KA'S) ANSWER-3.02' (2.50)

a. 1. Stator Coolant Pressure (0.25) 13 psig (0. 25 ) 3 7 s* STE#~ ## "#I

2 Stator Winding Coolant Outlet Temperature (0.25) 81 C (0.25) .b. Three-(3) minutes (0.25) c' A turbine trip is initiated (0.25) if load is not reduced to 75% (0.25) in two-(2) minutes (0.25) OR'to 25% (0.25) in three and one half (3.5) minutes (0.25) REFERENCE Perry Nuclear Power "lant' System Description Manual Main Generator pp 12 and figure N41-9 245000K508 245000K406 245000K402 245000K201 ...(KA'S) I (

) T 3. INSTRUMENTS _AND_. CONTROLS PAGE: 39 ) .; s - ANSWERS'-- PERRY 1&2 -87/06/01-DANIELS, M.. y ,4

• ANSWER 3.03.

(2.00)- ) s l a. 3 and 5 (0.50)- b.:2 and 3- (0.50) c. 2 and 3 .(0 50)' d; 3 and 5 .(0.50) j '(8. required at 0.25 ea) ' REFERENCE Parry Nuclear Power Plant System Description Manual Instrument Air System :pp 7 223001K403 223001K101 112001K102 ...(KA'S) 'ANSWERf ~3'.04 (1.50') 9 ,n. APRM's on scale b.'IRM/APRM' overlap check has been c'ompleted

c. The: Reactor Mode Switch is in.RUN

/, //s/%dt ;i n /n/v/of /hm .(3 required.at 0.50.ea) REFERENCE t

Parry Nuclear Power Elant System Description Manual Intermediate Range Monitoring System pp 27' 215003K503 215003K405 215003K1061

-215003A101 ...(KA'S) l ANSWER 3.05 (1.00) d (1.00) . REFERENCE .Porry Nuclear Power' Plant System Description Manual Power Range Monitoring System 215005K501 215005K104 ...(KA'S) __m _.. ___._..m

3, INSTRUMENTS AND CONTROLS PAGE 40' p1 l ANSWERS - : PERRY,1&2 -87/06/01-DANIELS, M. LANSWER 3.06-(1.25)' .a.. Containment Evacuation (0.25) ,'l '(0.25)

b. Containment'

c. Drywell (0.25)

.d. Fuel Handling Building (0.25) l u

e. Revolving Red: Lights (0.25)

'(b, c and d may be in any order) REFERENCE Perry' Nuclear Power Plant System Description Manual . Airborne Radiation-Monitoring System-pp 14 '272000K122-272000K119 272000K110 272000A101 ...(KA'S) . ANSWER. 3.07 (1.00) a.' DECREASE (0.50') ~ b.' INCREASE (0.50) REFERENCE-BWR Academic Series Instrumentation and Control ~216000K514 216000K513 216000K501 ...(KA'S) ' ANSWER 3.08 (1.50)

a. Depressing one (1) pushbutton deenergizes one solenoid of the Scram

-Discharge Volume (SDV) pilot valves, but no valve repositioning occurs. (0.50)

f. Depressing both buttons, deenergizes both solenoids for SDV pilot valves and the vent and drain valves go closed.

(0.50) C;)(. Valve position indication for the valves is provided on panel 4 p680. (0.50) ' REFERENCE Perry. Nuclear Power Plant System Description Manual Reactor Protection System pp 5 i

7:. .3; INSTRUMENTS'AND CONTROLS -PAGE 41 q ~ ANSWERS -- PERRY'1&2 -87/06/01-DANIELS, M. 212000A412 212000A409 ...(Kh'S) I LANSWER 3.09-(2.00) a. 5 or 7 (0.50)

b. 8 (0.50) c.

4-(0.50) d. 1 (0.50) ' REFERENCE Perry Exam Bank 264000K505 264000K502 264000K503 ...(KA'S) k of $4 U*b et y go l'g/N .l ANSWER 3'.10 (.50) / No. automatic action takes place, the logic to isolate the Off1 Gas System is 1 -two-out-of-two. (0.50) REFERENCE H

Perry-Exam Bank 272000K402 272000K106

...(KA'S) .) U ANSWER 3.11 (1.00) i b. (1.00) REFERENCE Perry Nuclear Power Plant System Description Manual l Remote Shutdown System pp 12, 13 295016K201 295016A107 ...(KA'S) 4 l l )

l 3. INSTRUMENTS AND CQNTROLS PAGE 42 ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. . ANSWER 3.12 (1.00) b.(0.50) Depressing either the "A" or "C" pushbuttons, deenergizes the "A" scram pilot solenoids. "B" or "D" pushbuttons must be pressed to de-energize the "B" scram pilot solenoids. Both sets of solenoids must be de-energized to complete the scram.(0.50) REFERENCE Perry Nuclear Power Plant System Description Manual Reactor Protection System pp 17 212000K108 ...(KA'S) ANSWER 3.13 (1.50) I

a. Alarm function and indication are lost on both the local and remote indicating units.

(0.50)

b. The signal from the local detector is transmitted to the Control Room Readout Module (0.50) which in turn sends a signal to the local and remote readout units. (0.50)

REFERENCE Perry Nuclear Power Plant System Description Manual Area Radiation Monitoring pp 2 272000A308 27200tA307 272000A203 272000KG03 ...(KA'S)

3.' ' INSIBQMENTS AND CQHIBQLS. PAGE 43 ANSWERS -- PERRY.1&2 -87/06/01-DANIELS, M. I i ANSWER 3.14 (1.50)

a. Limits steam line flow, on a steam line break, to ~200%

i of rated flow. OR Limits steam line flow to protect the steam dryer and other reactor components

b. Provide' steam flow signals to the feedwater system for RPV level control

c. Provide steam flow indication d.. Provide delta p flow indication to the' main steam line isolation logic, for closure of the MSIV's.on a steam line break (Any 3 @ 0.50 ea)

REFERENCE Parry Nuclear Power Plant System Description Manual i Lsak Detection System pp 8 i M2in Steam System pp 7 239001K606-239001K505 239001K404 239001K401 ...(KA'S) ANSWER 3.15 (2.00) a.1 ARI Keylock Test Switch (0.25) 2 Manual Initiation (0.25) 3 3 RPV Level, less than Level II (0.25) 4 RPV pressure greater than'1083 psig (0.25) b.1 Manual Initiation (0.25) 2 RPV Pressure' greater than 1083 psig (0.25) 3 RPV level less than Level II (0.25)

c. APRM not downscale (0.25)

REFERENCE Parry Nuclear Power Plant System Description Manual R2dundant Reactivity Control Figure C22-2 295037K203 295037K202 295037A103 295037A102 ...(KA'S) l

pr- - 3

3. ' INSTRUMENTS AND CONTROLS PAGE 44 1

.i ANSWERS 1-- PERRY'l&2- -87/06/01-DANIELS, M. ANSWER 3.16 (1.00)

a. Failure of the number one (1) seal will result.in an increase in the number two (2) seal pressure (0.25) and an increase in the staging flow through the number two(2) orifice (0.25)

b. Failure of the number two (2): seal will result in a lower

. pressure in the number two.(2) seal (0.25) and an outer seal " flow high" alarm. . REFERENCE Perry Nuclear Power Plant System Description Manual Reactor Recirculation System 202001A110, '202001A109 ...(KA'S) ANSWER 3.17 (2.25) l

a. The absolute. difference between the-actual-flux and the estimated flux exceeds 5% (0.50) or APRM actual flux exceeds

.110%. (0.50)

b. The: absolute difference beteen the actual flux and the estimated flux is less than 2.5% and. decreasing,(0.50) or the APRM. actual flux has decreased to less than 105% (0.50)

c. The light illuminates if-the estimator circuit has automatically switched between the estimated signal and.thg u

actual signal, 200 times in a ~ five (5) minute period (a,2r/ ) REFERENCE Perry Nuclear' Power Plant System Description Manual Reactor Recirculation and Recirculation Flow Control System pp 29, 30 202002K102 202002K103 ...(KA'S) I i

d '. ' PROCEDURES - NORMAL. ABNORMAL. EMEEGENCY.AND PAGE 45 RADIOLOGICAL CONTROL ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. ANSWER 4.01 (1.00)

a. Fail Closed (0.50)

b. Fail open (0.50)

REFERENCE f -Porry Nuclear Power Plant Off Normal Instruction ONI R2J-1 pp 16 262001K302 ...(KA'S) ANSWER 4.02 (2.00) l 1

a. Auto Start

b. Auto Trip c.' Auto Close d.

Isolates (4 @ 0.50 ea) i REFERENCE Parry Nuclear Power Plant Off Normal Instructions ONI911 pp 2 262001K302 262000K301 ...(KA*S) i

4.

' PROCEDURES'- NORMAL. ABNORMAL. EMERGENCY AND. PAGE 46 .B&DIOLQQICAL COjgBQL ANSWERS'- ' PERRY 1&2 -87/06/01-DANIELS, M. l 1 l ANSWER 4.03' (2.00)'

a. Arm and depress the PPS MANUAL SCRAM CH A, B, C and D pushbuttons.

j 1

b. Place the REACTOR. MODE SWITCH in SHUTDOWN.

c.' Verify all control rods are inserted and that thermal power is ' decreasing

d. Trip the Main Turbine, by depressing the TURBINE TRIP PUSHBUTTON.

e... Place the Division III Diesel Generator Diesel Control Transfer Switch to LOCAL

f. Transfer the Station Loads to the Startup-Transformer.

(4 required at 0.50 ea) REFERENCE Perry Nuclear Power Plant Off Normal Instruction ONI-C61 pp 1, 2 295016K302-295016K301 295016K303 ...(KA'S) i ANSWER 4.04 (1.00) l

a. Sound the Plant Emergency Alarm.

b. Announce " Evacuate the Containment" (0.50 ea)

REFERENCE - Porry Nuclear Power Plant Off Normal Instruction ONI-C-71 pp 3 295032K101 ...(KA'S) l '

NORMAL. ABNOEMAL. EMERGENCY AND 'PAGE 47-i LA. PROCEDUPRA t . RADIOLOGICAL CONTROL j ' ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. l ' ANSWER 4.05-(1.50) i 4rrfomplete boron mixing may not have taken place, and the slow a. cooldown rate limits the amount of positive reactivity added due to moderator temperature decrease (0.50)

b. Cooldown.is initiated by use of the BYPASS VALVE OPENING JACK l

(0.50) and is maintained at less than 50 F/hr by adjusting the { opening of the bypass valves. (O.50) Ahu -tI o.c<<r e < c. W o.t f,.., % o 3.%y., ew t c of,.,.3 _. % %. m, c u.,4. m. -.,. y ~2..- i, y REFERENCE D I-

• Wc 14ffA-c g a4 7 " g u * 'c /'5 d 's-Perry Nuclear Nw'e&'P'll[yidegYaTed' g)fatin,g!,'YnNu(cf, ion r

t pe ct -10I-13 pp 5 Parry Nuclear Power Plant Integrated Operating Instruction 101-1 pp6 i 239002A104 211000G005 ...(KA'S) l ANSWER 4.06 (2.00)

a. Never

b. Fifteen (15) minutes' i

c. Thirty (30) minutes

d. One (1) hour (4 @ 0.50 ea)

REFERENCE Parry Nuclear Power Plant Integrated Operating Instruction IOI-3 pp 1 201002G005 201002G010 ...(KA'S)

1 14:. 'PRQQEDUBES --NORMAL. ABNQBMAL_EMEB9ENGLAHp. PAGE. 48 RADIDLQQICAL_.CQHIBOL ~ ANSWERS --~ PERRY'l&2' -87/06/01-DANIELS, M. 4 ANSWER-4.07. (1.50)

a. Manually open the Bypass Valves by depressing the BYPASS OPENING:

JACK INCREASE pushbutton, and bypass steam to the main condenser to control pressure.

b. Place Recire Loop A and B controllers in MANUAL and reduce recire

' flow to minimum. ] 4 c.=When Recire Pumps are at minimum. flow, shift the pumps to low speed. (3 @ 0.50 ea) REFERENCE . Perry Nuclear Power Plant Off Normal Instruction ONI-C85 pp 2 295997A105~ 295007K305 295007K201 ...(KA'S) ANSWER 4~.08 (1.50)

a. Maintain-steam flow / feed flow balanced and react'or vessel water

-level within the normal operating range of.197 to 205 inches (.25) by reducing recirc. flow and/or restarting the reactor feed pump. (0.25) 1 m ted to 80* 05 c. If the Motor Feed Pump is unavailable and operation continues with one (1) RFP, reactor power is limited to 60% REFERENCE Perry-Nuclear Power Plant Off Normal Instruction ONI N-27 pp 2-3 295008K202 259001K312 259001K301 ...(KA'S) l ANSWER 4.09 (1.00) Reduces the rod block to less than or equal to 12% (0.50) and the l scram to'less than or equal to 15%. (0.50) REFERENCE l Perry Nuclear Power Plant-Integrated Operating Instruction IOI-4 215005K101 ...(KA'S) I \\

g: 74.* PROCEDURES -:NORMALi ABNORMAL. ElfgBGENCY ANDL PAGE-49 RADIQLQGICAL.COHIBQL l JANSWERSJ-- PEo.nY.1&2 - -87/06/01-DANIELS, M. ANSWER -4.10 (1.00)

a. There is fuel in the, reactor with the head closure bolts less than fully tensioned or, with the head removed (0.25) and the-average reactor coolant temperature is less-than 140>F (0.25)

b. SHUTDOWN (.25) or REFUEL (0.25)

REFERENCE:

Perry Nuclear Power Plant Integrated Operating Instruction IOI-9 pp'l 294001A113 ...(KA'S). ANSWER. ~4.11 f2.00) 'pg w // /oWf9/1 OK. cov % M.w i o w ~ :* 'l

a. C:ntain;0nt pressure reaches 1105 -M 0. 5 0 } f."' c:nt in;;n L

[lb,\\ w br L a.' v e n*" N.. # escure exceeds &?5 reis. 6M a a ZF \\;ht L*ya t o p c.sa n n e. fob o

• c p% gyp,gy yypp & C, ft n

a

b. Initiate Containment Spray (6-69)

.. - -.n centrin; nt -um temperature ' belex 1o5 F. (0--50) vu/r q o,fr) z + u s u s t + n u n<.e o a -a v r<- Wp s + n i.,n A a '. n :+. 4 e & ;'~ c ~_ . REFERENCE

1. / ' ' O * d # N # * # ' "#

0 C *' ' M Parry' Nuclear Power. Plant Emergency Instruction PIE-D23-1 pp 6 Parry Nuclear. Power Plant Off Normal Instruction ONI Rio pp 2 3 226001K110; ...(KA'S) ANSWER 4'12 (1.50)'

a. RPV level is less than 16.5 inches (0.50) or cannot be

' determined. (0.50) l

b. The hydrogen concentration in the containment or drywell l

exceeds 0.5% (0.50) REFERENCE l Parry. Nuclear Power Plant Emergency Instruction PIE-M51/56 pp 2 294001K115 ...(KA'S) i i

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 50-.

RADIOLOGICAL CONTBQL ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. I ANSWER 4.13 (1.75) i

a. A yellow' tag is placed on a piece of equipment to warn operating representatives.that a ground (or grounds) have been placed on the circuit'.

(0.25) -b. This'is a violation of the tagging procedure (0.25) A yellow tag is not to be hung without a red tag.(0.25)

c. A switch cap is a form of tag for switches. (0.25)

d. The tag can be either red or white (0.25) e.

The cap is used on the Main and Rad Waste Control Room Panel Switches. (0.25) Used when a large tag would obscure instrumentation, or hinder operation of adjacent control' switches. (0.25) REFERENCE Parry Nuclear Power Plant Administrative Procedure PAP-1401 pp 5 294001K102 ...(KA'S) ANSWER-4.14 (1.50) a. 5

b. 2

c. ff

d. 5 e.

2

f. 4 (6 required @ 0.25 ea)

REFERENCE Parry Nuclear Power Plant Operations Manual Control of Lifted Leads, Jumpers, Temporary Electrical Devices and Machanical Foriegn Items PAP-1402 pp 3 294001K102 ...(KA'S) ______--___ j

4. PROCEDUBES - NORMAL. ABNORMAL. EMEBGEHCLAND PAGE 51 BADIDL991 CAL _CQHIBOL ANSWERS!-- PERRY 1&2 -87/06/01-DANIELS, M. ANSWER 4.15 (1.00) a. If a reactor scram has not been initiated, then arm and depress.the RPS MANUAL SCRAM pushbuttons.

b. Place the REACTOR MODE SWITCH in SHUTDOWN

c. Place the hydrogen analyzers in service

/, Ex tevrt / f,/hs h/nj / (2 required at 0.50 ea) {u L funsn AW16Cl ud 91/ toe / s.:,< rhelf e Mtwyenn y' Parry Nuclear Power Plant Emergency Instruction PEI-B13 pp 4 295025G010 ...(KA'S) ANSWER 4.16 (1.75,)f ~ Any of the following conditions;

a. Reactor level is less than 177.7' inches or cannot be determined.

(0.25)

b. Reactor pressure is greater than 1065 psig.

(0.25)

c. A condition exists which requires MSIV isolation.

(0.25)

d. Drywell pressure is greater than 1.68 psig.

(0.25)

e. A condition exists which requires a reactor scram. (0.25)(0.75)

AND Reactor power is above 4% (0.25) OR Reactor power cannot be determined (0.25) REFERENCE Perry Nuclear Power Plant Emergency Instruction PEI-B13 241000K303 241000K102 ...(KA'S)

4.* PRQQEDURES - NOBHAL. ABNORMAL. EMERGENCY AND PAGE. 52 RADIOLQQ1QAL CONIBQL ANSWERS -- PERRY 1&2 -87/06/01-DANIELS, M. ANSWER 4.17 (1.00)

a. A channel check is the qualitative assessment of channel behavior, by comparing, where possible, with other-indications from independent instruments monitoring the same parameter. (0.25)

b. A' channel calibration is an adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy, to known values of the parameter which the channel monitors.

(0.25)

c. A Channel Functional Test for analog channels consists of injecting a simulated signal as close to the sensor a practicable, to verify operability of alarm and/or trip functions and channel failure trips.

(0.25)

d. A Channel Functional Test for a Bi-stable Channel consists of injecting a simulated signal INTO the sensor to verify operability, including alarm and/or trip functions.

(0.25) REFERENCE Parry Technical Specifications Section 1.0 Definitions 212000A402 215005G001 215005G002 215005G006 ...(KA'S) l i I _____________________J}}