ML20204G772

Exam Rept 50-305/OL-87-01 During Wk of 870216.Exam Results: Two Senior Operator Candidates Failed Exam & Two Senior Operator & Two Operator Candidates Passed Exam.Exam Encl

ML20204G772
Person / Time
Site:	Kewaunee
Issue date:	03/19/1987
From:	Burdick T, Damon D, Reidinger T, Sunderland P, Victor F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20204G758	List: ML20204G752 ML20204G772
References
50-305-OL-87-01, 50-305-OL-87-1, NUDOCS 8703260459
Download: ML20204G772 (130)

Text

{{#Wiki_filter:r .t-n l U.S. NUCLEAR REGULATORY COMISSION REGION III Report No. 50-305/0L-87-01 Docket No. 50-305 License No. DPR-43 Licensee: Wisconsin Public Service Corporation Post Office Box 19002 Green Bay, WI 54307-9002 Facility Name: Kewaunee Examination Administered At: Kewaunee Nuclear Power Plant Examination Conducted: Week of February 16, 1987 Examiners: 7/7N6 3//f[(7 I. - T). Reidinger " Date GRSmA6t A s/m/a7 P. R. Sunderland Date 3]I9l87 D.U. Damon Date k/9M F. W. Victor y Date ' ' Approved By: # A 3)l947 I. M. Burdick Date'l Operation Licensing Section Examination Summary Examination administered on week of February 16,1987 (Report No.50-305/0L-87-01) Examinations were administered to four senior operator and two operator candidates. Results: Two senior operator candidates failed the examination. B7032604S9 070320 PDR ADOCK 0500 5 V i

3 i! ' '.f REPORT DET l'S L \\ ,1 1. Examiners 'I ' T. D. Reidinger, N3C Region III P. R. Sunderland, FRC Region III D. J. Damon, NRC Region III J F.' W. Victor, Sonalysts Inc. 2. Examinatiod Review M_e_e_t_ing A copy of the examinations and answer keys was given to the facility personnel for eqview at the conclusion of the written examination. Facility personnel mailed their concents to the Chief Examiner ef ter ,j their review. Their conments and resolution of these connents are s Attachment I to this report. 3. Exit Meeting On February 20, 1987, at the conclusion 7,f ne replacement examinati.ons, the examiners met with nsbers of the piant staff to discuss findirigs made during the course of the examinations. The following personnel attended the exit meetio p C. Steinhardt, Fatility Plant Manager D. Braun, Facility Superintendent, Plant Operaticns-K. Evers, Facilitj Assistant Manager, Plant Operations F. Stanasrak, Facility Training Supervisor R. Zube, facility Sin:ulator Supervisor J. Brown, Facility Training Instructor D. Kwaitkowski, Westinghcuse Site Services Manager R. Nelson, NRC Senior Resident Inspector T. Reidinger, NRC Examiner P. Sunderland, NRC Examiiier D. Damon, NRC Examiner J. Lennartz, NRC Examiner i The following areas were discussed: .s a. Generic weakness exhibited by the candidates'fMluded: (1) Candidates fa'lled to consistently use abn(rn'al procederes, ~ t6 corfirm the correctness of actions ?ak en after a d.sualty. I (2) Coninunications should be improved, with the SR0 providing a n; ore visible leadership role. / 2

1lt, V3 b. Generic strengths noted included: (1) Use of normal procedures was very good. c. (2) Candidates were well versed in administrative requirements. c. The following concerns were discussed by the examiners. It is (4( requested that the utility provide a written response addressing both of these concerns. 2 4 i l (1) There is a need for a specific procedure that addresses 'i bistables to be tripped following an instrument failure that } provides formal verification that the proper bistables are tripped. Currently, the bistables to be tripped are in separate ( surveillance procedures. It was suggested that an interim c g, procedure could be a partial surveillance procedure sign-off that includes the proper bistables. A,q I'/ (2) Malfunctions on the simulator that do not work need to be 'I'" f identified and corrected. A specific malfunction that did not '(,. work for this set of scenaric was TUO1 - Turbine Vibration. The utility generated list of...alfunctions that do not work is c Attachtrent 2. i U p D ) \\ )\\ i s c\\ 6,, / b.' i \\,. \\q n ,.A )m 3 4

ATTACHMENT 1 Exam Comments and Resolutions il Reactor Operator Exam QUESTION: 1.06 Facility Comment: Clad creep is.oredominant in fresh core, however Kewaunee trains that in subsequent loads buildup of PU-240 is the overriding effect. Resolution: Comment not accepted. The KNPP Operator Training Manual is unclear as to what the most dominant factor is and the facility reference chart was not provided as a reference to the NRC. The buildup of PU-240 is accepted as a correct answer. 1 o QUESTION: 1.07 Facility Comment: Operators at KNPP are trained to use the Accumulated Integral Rod Worth Tables'vice'the individual bank integral rod worth curves which were given oc. this exam. This is due to the inaccuracies of utilizing a curve whfan only reflects the " individual" bank with all other banks out of the core and the inherent inaccuracies in reading a curve.vice reading a table. With this in mind, a larger tolerance should be allowed on the final answer. Resolution: The NRC recognizes the training methods utilized by training staff. QUESTION: 2.01 Facility Comment: Valves may also be'given by nomenclature and not number. "FCV" numbers are not used by operators. Resolution: The NRC recognizes that "FCV" numbers are not used by opsrators. 4

13 ? ~, ,s s, , QUESTION: 2.02 Facility Comment: Question does not specifically solicit answers given in key. Alternate ' answers could be given which would be sufficient for full credit given the question's wording. i.e., a.1 Hydrogen is added to control oxygen content in the RCS. -a.4 Nitrogen is added as a cover / fill gas to the CVCS holdup tanks. NOTE: On a.2. It is true that Hydrazine scavenges dissolved oxygen at low temperatures; however, the "why" hydrazine is added is because hydrogen won't scavenge oxygen at plant conditions where flux is minimal. (i.e., no recombination will take place). b. The examinee may include the general steas involved in adding chemicals via the chemical mixing tank w1ich are contained in procedure N-CVC-35C. KNPP does not require nor encourage rote memorizationofnormalprocedures,butthemajorstepsandgoalsare emphasized. We have included the detailed procedure as a reference guide for grading purposes. Resolution: E Comment a.1 not accepted. Facilitycommentjustrewordstheanswerkey. Comment a.4 not accepted. Facility reference is about Gas Decay Tanks which are not part of the CVCS, nor does the referenced vent line to the CVCS holdup tanks include any purpose. Drawing XK100-37-P does show the N2 cover gas for the holdup tanks so the answer key is modified to include this answer. Comment b not accepted. The question is not soliciting a procedure to be memorized. The candidate should know the flowpath and flow control is as requested. E QUESTION: 2.04 Facility Comment: 2.04.d Charging pumps are not cooled by CCW. Alternate answers - cooled by air or pistons cooled by oil bath which is cooled by air. Resolution: Comment not accepted. Facility references only prove that CCW does not cool the charging pumps (XK100-19, 20). Facility reference XK100-35 is not related to the question, however, XK100-36 and M-604 show air cooling of the pumps. Answer has been modified to accepted air cooled. 5

QUESTION: 2.07 Facility Comment: Wording of question is not consistent with KNPP terminology. The " NORMAL" power source is not the same as the " preferred" power source as implied by question wording and structure. Nor is the " STANDBY" power source the same as the " alternate" power source. (See Reference Drawing E233.) This confusing wording may lead to soliciting only that two sources are required to be shown. NOTE: Answer key sketch in error on battery. See reference. Resolution: Comment not accepted. Wording of question is consistent with KNPP terminology. Drawing references the stated terms, standby, normal, preferred and alternate. Full credit will be given for any combination which provides at least two methods of powering Instrument Bus No. IV from MCC 1-52C 480 VAC bus. QUESTION: 2.08 Facility Comment: 2.08.a Provides cooling water for the turbine drive bearing cooler is applicable to only the Turbine Drive Aux Feed pump. Alternateanswer(s)couldbe- - Provide for condensate conservation by recirculation path back to CSTS. - Provide for surveillance testing. Resolution: Comment not accepted. The recirculation system does not limit answers to both types of Auxiliary Feed Pumps. Also conservation of condensate is not accepted from the reference material as the material was supporting Answer a.1 at the time. QUESTION: 2.10 Facility Comment Operators are trained to " list" Stop Lockouts as shown on reference. Especially when setpoints are not required. 6

I O I Acceptable (full credit) answers should be: 1. Overspeed 2. Low Jacket Water Pressure 3. Start Failure 4. Low Oil Pressure Resolution: Comment not accepted. Set 30ints in parenthesis were not required for full credit as stated in tie question. However, for full credit, the candidate is required to state that the diesel speed sensing switch is activated. QUESTION: 2.11 Facility Comment: KNPP utilizes helium filled balloons and air. Smoke is not used. Resolution: Comment is not accepted. Reference SP 23-096 which was not provided appears to conflict with SD 23 which was provided. QUESTION: 2.12 Facility Comment The question could confuse examinee due to " interlock" - implies a condition which prevents an occurrence. The question would be better worded as " Describe what events occur with a MSIV closure". Resolution: Comment is not accepted. The term interlock comes directly from the reference material. QUESTION: 3.01 Facility Comment: Part C of the question could solicit additional answers. Such as: - Turbine Trip - MDAFW pumps start Depending on plant conditions assumed, the answer could also include: - Turbine runback initiated 7

Resolution: Comment not accepted. To start a Motor Driven Auxiliary Feed Pump, both Main Feed Pumps must trip per the facility reference. The question specifically states only the Main Feedwater and Condensate Systems should be considered. QUESTION: 3.02 Facility Comment: A more detailed answer could have been listed to Part B depending on candidates perception of what depth was necessary to answer this question. See referenced lesson plan. Resolution: Comment not accepted. Answer is consistent with reference and point value. QUESTION: 3.04 Facility Comment: Answer should include: 8. Both Reactor Coolant Pump Breakers open. Resolution: Comment accepted. Answer modified to include, 8. Both Reactor Coolant Pump Breakers open. QUESTION: 3.05 Facility Comment: Answer item #4 should be split and therefore allowed as two separate answers. This is consistent with items 2 and 3 being allowed as two separate answers. Resolution: Comment noted. 8

o r QUESTION: 3.09 Facility Comment: Part B of this question is wide open to a vast set of variables. When the first automatic start attempt is unsuccessful - why'was it unsuccessful? Was it because the starting air pressure didn t reach 85 psi, didn't the pinion gears engage, or maybe the primary pair of starters malfunctioned? Depending on all of these various possibilities and/or combinations of these, the examinee could have answered anywhere from two to seven additional starts. The more important fact is that if the fifteen second timer times-out, an engine start failure occurs. Resolution: Comment not accepted. The question did not state any assumptions or prior conditions. However, if the candidates stated any assumptions, then their answers will be addressed accordingly. QUESTION: 3.11 Facility Comment: Answer key error on a.1 - should read > 23.5" Hg vacuum. Additionally, answer may include the setpoint for bypass interlock of 10" Hg vacuum. Resolution: Comment noted. An answer of > 23.5" Hg vacuum receives full credit. QUESTION: 3.13 Facility Comment: Answers solicited may go beyond answer key to the items specifically being affected by relays. Example: - 86/MTB1A and 86/MTB1B cause G-1, 3450, 3451 trip and lockout. NOTE: The Emergency Diesel Generator start is from a Turbine Trip signal - not direct from 86/T1A or T1B (SD No. 43 in error). Resolution: Comment not accepted. The question specifically asks about lockout relays 86/T1A and 86/T1B, not 86/MTB1A and 86/MTB1B. The NRC acknowledges the error in KNPP SP43. The error is expected to be corrected by the utility prior to the next scheduled examination. 9

T.. QUESTION: -4.02 Facility Comment: . Part A is wide open to a vast number of different scenarios. Example: - blocked filters - closed isolation valves Even the given answer could be in error if the assumption was that. inlet i-pressure was low thereby not causing a delta p to operate the bypass - valve. Resolution: ~ Comment not accepted. The cause is consistent with the stated reference. If the candidates made certain assumptions then consideration will be i given to those-assumptions and will be graded accordingly. i-QUESTION: 4.05 Facility Coment: All blowdown valves and sample valves close. R-19A and B have not been installed yet. KNPP~has R-19-for both "A" and "B" steam generators. Resolution: 7 Coment accepted. Part A of the answer has been modified to state "all S.G. blowdown valves shut and all S.G. sample valves shut." . QUESTION: 4.11 Facility Coment: . Additional action on pipe break could include: - Establish alternate decay heat removal with the steam generator or if l the RCS is depressurized, with Step 4.5. Resolution: Coment accepted. Answer has been modified to include additional action, "Establishalternatedecayheatremovalwiththesteamgeneratororif the RCS is depressurized i f 10 ..,-,u ,,.-.,------~-,.----,,..-,,-,---.,,---.--,.w, -,l-,, ,,..~.--.w.,., --n, ,n c., --,,~ -. ~n ,..ev.--,---.

i Senior Reactor Operator Exam QUESTION: 5.04 Facility Comment: Wordingofpossiblechoicesisveryconfusingw"hichcouldleadto examinee selecting of the wrong item. Item D given as the definition is, in fact, not defined in KNPP Technical Specifications in this manner. Resolution: Comment accepted. The question is deleted. QUESTION: 5.08 Facility Comment: Similar wording should be acceptable. Questioncouldsolicitmore " operationally-oriented" advantages than design and/or theory type advantages. Resolution: Comment not accepted. No operationally - oriented advantages provided by the utility. No other references wera provided. QUESTION: 5.09 Facility Comment: The quoted reference utilized pertains only in a general sense to this question. The answers which may be solicited could vary considerably depending on assumptions made by examinee. Resolution: Comment not accepted. If assumptions are stated by the candidate, the answer is evaluated according to the assumption if the assumption is deemed valid. Utility did not provide any references or assumptions that will support the comment. QUESTION: 5.10 Facility Comment: a. A more detailed definition of AFD may be given that is still acceptable? 11

AFD'= (P - P ) x 100 percent T B where P

• I'r T

I 100 percent T P I' B

• I 100 5ercent g

c. A more complete answer may be given, which includes information not in exam key. "At full power, the water leaving the reactor (Tu) is much hotter than the water entering the reactor (Tc). The hatter Tu (as power increases) causes the flux to be supprussed in the top Of the core (more negative MTC at higher temperatures) forcing the flux peak to shift downward..." Resolutir 1: Comment accepted. Answer key was modified to accept both conditions. However, the question did not solicit a formula derived definition in Part a. Comment from utility in Part c is a generalization of the stated answer key. QUESTION: 5.11 Facility Comment: More specific information may be given such as: " Temperature below RT " vice "Relatively Low Temperature." NDT Resolution Comment accepted. Answer key modified to add comment.

However, the stated answer is specifically noted in the reference mentioned.

QUESTION: 5.15 Facility Comment Tolerance on final result should be greater. Allowed tolerance on reading RD 6.2 and RD 8.1 could result in a larger variance on final answer than that given. Resolution: Comment not accepted. The allowable tolerances in the answer will be in the the range of 3.18 through 3.36. This is within the.1 allowed by the answer key. 12

QUESTION: 6.01 Facility Comment: Examinee could interpret item #1 in right hand column as meaning "either" channel and item #2 as meaning "both" channels are needed to do it. If an examinee did make this interpretation, then the answers would be: a. 1 b. 1 c. 1 d. 2 Resolution: Comment accepted. To eliminate any potential confusion from the candidates, Item B will be deleted from the examination. QUESTION: 6.02 Facility Comment: b. DG 1A Oil Cooler is cooled by the JACKET WATER COOLING SYSTEM which is in turn cooled by service water. Resolution: Comment accepted. Answer key modified to reflect comment. However, the stated reference notes that the service water control valves are provided to the diesel Generator 1A/1B oil coolers (CV 31088/31089). The utility reference was not provided prior to the examination. QUESTION: 6.03 Facility Comment: Correction to Question Slackcablesetpointonmanipulatorcraneis500lb(vice450) asper Westinghouse Refueling procedure FP-WPS-R11, Rev 0 (SD No. 53 error). Resolution: The NRC acknowledges the utility's recognition of the error in KNPP system description Page 53-16. The utility is requested to provide the correction prior to the next examination. 13 . - ~, _

t QUESTION:~ 6.04 Facility Comment: An additional answer "The capacity of the refueling water storage tank is based on the requirement for filling the reactor refueling cavity..." Should be allowed. Another additional answer "... refueling water storage tank conditions specified are consistent with those assumed in the LOCA analysis." Should also be allowed. Resolution: Filling the refueling cavity is an additional operation for a correct answer. However, the utility's additional answer is not accepted because it is not considered to be a basis and is discussed by the first three answers. QUESTION: 6.09 Facility Comment: l Additional answers should be accepted which are in accordance with items shown on reference drawings E1634 and E1636. Item c.7. should read "... not in PULL-00T." Resolution: Comment not accepted. The utility drawings reflected the stated answer key, no additional answers were discerned per the drawings. Item c.7 typographical error "not in pull-out" was amended. QUESTION: 7.10 Facility Comment: Acceptable answer on Part B could be anywhere from 100 psig to 106 psig based on referenced SP. Resolution: Comment not accepted. KNPP OP Procedure E-FP-08 does not allow this tolerance range. l 14 l w rm-s .._-y y. g. y m,-- - -- - -g- - - - - - - y-w,- y-- -=y---- - %w - - --*--i

QUESTION: 7.11 . Facility Comment: Format of answer key in error. Should be: a.1. RCS Subcooling based on core exit TC's < 30 F

2. PZR level cannot be maintained > 2%

b.1. RCS Subcooling changes to < 120 F

2. PZR level changes to > 20%

Resolution: Comment accepted. The mislabeled answer key was amended noting that the answer key is still correct. QUESTION: 7.12 Facility Comment: In Part B - Utilizing procedure N-RC-36A, 3.0 note, as well as the Westinghouse RXCP. Instruction Book 5710-838-1, Pump: Section 6, there is no allowance for the omission of ANY of the initial conditions. Although the answer solicited comes from the cited reference, the question itself (as written) requires the answer "NONE" if one were to use only N-RC-36A. However, in the emergency procedure FR-C.1 a NOTE preceding Step 17 allows the omission of the initial conditions given the conditions applicable to the procedure. Resolution Comment not accepted. The note clearly states what the answer of Part B demands. The NRC notes that the utility recognized the stated answer is correct. The utility did not provide the Westinghouse RX CP instruction Book 5710-838-1. QUESTION: 7.14 Facility Comment: Note calculation error in answer key: a. Distance 1 = 1 ft (D ) 1 Distance 2 = 4 ft (D ) 2 l l l l 15

.:o Dose 1 = 800 mr/hr (I Dose 2 = x (I ID2=ID2 1 1 22 (800) (1)2 = (x) (4)2 800 = 16x 800/16 = x 50 mr/hr = x (Answer key has 30 mr/hr) 50 mr/hr x 3 = 150 mr (Answer key has 90 mrem) Resolution Comment accepted. Answer key was modified to reflect the typographical comment. QUESTION: 7.16 Facility Comment: Answer Key Correction a.3. Screenhouse Header Isolation A is SW 3A/CV 31038 (not 31040). Resolution: Comment acce)ted. Answer key was modified to accept the optional answer of valve num3er. The valve number was not required for the answer but was considered an option by the candidate. QUESTION: 8.01 Facility Comment: Answer is correct PROVIDED: 1. Its corresponding emergency power source is operable; and 2. Its redundant system, train, or component is operable. (No information was given in question related to these twoprovisions.) Resolution: Comment not accepted. The facility comment is exactly the reasoning required to produce a correct answer of False. The answer key and question remain unchanged. 16

F QUESTION: 8.03 - Facility Comment: Answer given in Part A only ensures control of entry, not that the CONTAINMENT SYSTEM INTEGRITY requirement is met. The SP for airlock leakrate test satisfactorily completed or the Containment Integrity Checklist satisfactorily completed would be an applicable administrative means of insuring CONTAINMENT SYSTEM INTEGRITY requirements is met. Resolution: Comment not accepted. The facility comment does not have any relationship to the answer being solicited. QUESTION: 8.04 Facility Comment: KNPP does not require nor desire the rote memorization of all possible reportables given on the Night Orders tables. We have the tables in Night Orders to preclude reliance on memory. We train our people to use 1. this ready reference vice relying on memory. Resolution: Comment not accepted. The SR0 should know requirements that have actions due within one hour. The NRC supports the utility's philosophy on not requiring rote memorization of possible reportable instances but one hour requirements should be the exception. QUESTION: 8.06 Facility Comment: Changes per ACD 1.8 Rev A i Independent verification may be accomplished by: 1. A qualified individual operating independently, physically verifying that a component has been placed in a specified configuration, or l 2. The performance of an independent functional test without compromising i plant safety that unambiguously verifies the component is in a specified configuration. Resolution: Comment accepted. The NRC notes that the utility did not provide an updated ACD prior to the examination. i 17 1 i ,~

w..,

QUESTION: -8.11 Facility Comment: The question in Part A solicits "the" major difference and the answer. key contains two differences. The " repetitive nature" vs. "non-repetitive . jobs" is the major difference. For information only - Part B refers to a RADIATION HAZARD AREA. KNPP definition of RADIATION HAZARD AREA is "any area where the p/hr orrobability exists of encountering general area radiation fields of 10 R greater." Resolution: Comment not accepted. The reference clearly states that the answer key is correct and was actually extracted verbatim from the reference. QUESTION: 8.12 Facility Comment: Answer in Part B is in error. The RWST does not fit into the 72 hour LC0. Within one (1) hour per KNPP Technical Specifications guidance letter dated August 15, 1984. NOTE: Additional reference of TS 3.3-2 for RWST level should be added to answer key references. Resolution: Comments not accepted. TS 3.2-2 was the only reference available prior to the examination. This specifically states that the answer key is correct as stated. The mentioned KNPP technical guidance letter was not provided prior to the examination, however, the one hour answer will be accepted. QUESTION: 8.13 Facility Comment: Part B may solicit much more than what is contained in key. Answers solicited may include items contained in referenced Technical Specifications which are applicable to a power increase from 35% up to 100%. Answer key is only one item. 18

Resolution: Comment noted. The utility did not provide any additional items to be considered. The candidate is required to at least state the requirement for AFD to increase power to above 50%. Any additional requirements prior to exceeding 90% power is considered an option for the candidate. QUESTION: 8.15 Facility Comment: Part B may only solicit " maintain RCS integrity." Resolution: Comment accepted. Answer key adds comment as alternate full credit answer. QUESTION: 8.17 Facility Comment: a. SHOULD BE " Restrict maximum core power level two percent for every one percent of indicated power tilt ratio exceeding 1.0." Therefore MAXIMUM power is reduce by 10%. Power limit is 90%. Resolution: Comment (a) is accepted. Answer key is changed from 85% to 90%. 19

_. ~. ...a s ATTACHMENT 2 Malfunctions that need to be corrected: ED06 Loss of 125 VDC Bus ED07 Loss of 118 VAC ED08 Loss of 4160V ED09 Loss of 480V ED11 345 KV Breaker Reclosure EG09 Generator Output Breaker Fails to Open Following Turbine Trip Condensate System Recirculation Valve Fails Open FWO2 FWO7 Feedwater Pump Recirculation Valve Fails Open TC05 Turbine Control System Cycling Turbine Blade Damage TUO1 I. l I i 20

F MASTER COPY f* U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _BgBAUNg[_),[____________ e REACTOR TYPE: _PHB-HEgg' ~

.m DATE ADMINISTERED: _Q229?til_____________-__

EXAMINER: _@UNQERLANQt_Pz__________ CANDIDATE: INSIBUGIIQUE_ID_G6NQIQeIE1 Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passins grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts. % OF CATEGORY % OF. CANDIDATE'S CATEGORY __20LUE_ 1916L ___SG9BE___ _266UE__ ______________Q61EGQBl_____________ _E9199__ _29132 ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS _23159__ _g9392 ________ 6. PLANT SYSTEMS DESIGN, CONTROL, i AND INSTRUMENTATION 3E199__ _?gz2@ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL _Z5199__ _Z513@ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS _2@igQ__ Totals l Final Grade All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature u _m__

t s i NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS L During the administration of this examination the_following rules apply: 1. Cheating on the' examination means an automatic denia19o(iyour application and could result in more severe penalties. -Jn as 2. Restroom trips are to be limited and only one candidate s't'a* time may ~ leave. You must avoid all contacts with anyone outsideEthe examination . room to avoid even the appearance or possibility of cheating. 3.- Use black ink or dark pencil goly 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 ggch section of the answer sheet. 8. Consecutively number each answer sheet, write 'End of Category __' as appropriate, start each category on a ogg page, write 901Y 90 902 11dt 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 ih gg linen between each answer. t

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 litgtgtung.

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.

1

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 GUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

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

c..e 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. .i i

i s j

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

a. Assemble your examination as follows: N k y'i (1) Exam questions on top. -; -:$f,Q (2) Exam aids - figures, tables, etc. - / t' (3) Answer pages including figures which are part of the answer. i b. Turn in your copy of the examination and all pages used to answer l 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 arear as defineu 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 i0 ,, t ]1 1 J i e c. o ,f ^ .._fk ' f i., )- 1'%'y ' 4 4 i w ,-,_,.,y-

---

,-,,,,__-r,,

,,___,,,,-,,_-,_,.,,,-,-,,r__3-,,,m-,,m.,r.,_,, ..,,,,,,.,_.,..-_, - m m , - _ _ r

r EQUATION SHEET f = ma y = s/t Cycle efficiency = (Net work out)/(Energyin) j 2 w = ag s = V,t + 1/2 at 2 E = mc KE = 1/2 av ,, (yf, y )fg 3, 3, g, g,-At 2 g g PE = agn Vf = V, + at w = e/t 1 = an2/t-1/2 = 0.693/t1/2 y =,,p. ,o

• 1/2#*MMW 2

A= [(t1/2)*I*b}3 4 aE = 931 am m = V,,Ao I, g, -h o Q = mCpat 6 = UA A T I = I,e~"* I = I,10-*/ M Pwr = W ah f TVL = 1.3/u sur(t) P = P,10 HVL = -0.693/u P = P e*/I a SUR = 26.06/T SCR = S/(1 - K,ff) CR = S/(1 - K,ffx) x CR (1 - K,ffj) = CR (I - Eeff2} SUR = 26p/t* + (s - p)T j 2 T = (t*/s) + [(s - s yIo] M = 1/(1 - K,ff) = CR /CR, j T = 1/(o - 8) M = (1 - K,ffa)/(1 - K,fft) T = (a - o)/(Io) SDM = ( - K,ff)/K,ff a = (K,ff-1)/K,ff = aK,f/K,ff t' = 10 seconds I = 0.1 seconds-I o = ((t*/(T K,ff)] + (a,ff (1 + IT)] / Idjj=Id 2,2 2 P = (I4V)/(3 x 1010) Id gd jj 22 2 I = oN R/hr = (0.5 CE)/c (meters) R/hr = 6 CE/d2 (f,,g) Water Parameters Miscellaneous Conversions I gal. = 8.345 lbm. 1 curie = 3.7 x 1010dos 1 ga]. = 3.78 liters i kg = 2.21 lbm 3 Stu/nr = 7.48 gal. 1 hp = 2.54 x 10 1 ftd Oensity = 62.4 1 /ft3 1 mw = 3.41 x 106 Stu/hr Density = 1 gm/c lin = 2.54 cm Heat of vacorization = 970 3tu/lem

• F = 9/5'C + 32 Hest of fusion = ia4 Stu/lem

'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 f t-1bf I ft. H O = 0.4335 lbf/in. 2

e I g. THEORY OF NUCLEAB_Pg8[B_PL6NT_QPE86TIgN _FLUIDgt_6ND PAGE 2 1 IHE859D186MICS A'I QUESTION 5.01 (1.00)

• f1

,<:t As moderator temperature i.ncreases, control rod worth for ';the controlling bank ________ (INCREASES, DECREASES, or REMAINS THE SAME):di, QUESTION 5.02 (1.00) During a reactor startup, the first reactivity addition caused the count rate to increase from 20 to 40 cps. The second reactivity addition caused the count rate to increase from 40 to 80 cps. Which of the following answers is correct? (There is only one correct answer) c. The first reactivity addition was larger. b. The second reactivity addition was larger. c. The first and second reactivity additions were equal. d. There is not enough data given to determine the relationship of reactivity values. QUESTION 5.03 (2.00) a. List the three largest contributors to total power defect in order of increasing magnitude at BOL. (1.5) _.b. The total power defect at a given power level becomes _____________ MORE NEGATIVE, LESS NEGATIVE, or REMAINS THE SAME) from BOL to EOL. (Fill in the blank) (0.5) QUESTION 5.04 (1.50) Kewaunee is operating at 50% power (steady state) with all systems in canual. If no operator action is taken, what effect (INCREASE, DECREASE, OR REMAINS THE SAME) will a 10 degree-F increase in circulating water temperature have on the following: (consider each separately)

a. Ciculating Water Pump Available NPSH?

(0.5)

b. Condenser Vacuum?

(0.5)

c. Condensate Temperature?

(0.5) k. I 'a '3 I l (xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)

D. THggBY_QE_NUgLg68_EQHEB_PL6NT_QPEB6TIQN, _ELyIggt_6NQ PAGE 3 IMEBdQQ1NodIGE ',i QUESTION 5.05 (1.00) i ). - The difference between the total pressure and the saturation' pressure at a given point in a centrifusal pump is known as ________".. (Multiple Choice) e. Minimum Required Net Positive Suction Head b. Available Net Positive Suction Head c. Total System Head d. Head Loss QUESTION 5.06 (1.00) Fill in the Blanks o. The t(1/2)(half-life) of I-135 is __________ (LONGER, SHORTER, THE SAME) than (as) that for Xe-135. b. The fractional change of the effective multiplication factor from critical is known as ________. (0.5) QUESTION 5.07 (1.50) List two significant advantages that counter-flow heat exchangers have over parallel-flow heat exchangers. (1.5) QUESTION 5.08 (1.50) If natural circulation has been interupted (not due to excessive steam flow), predict if the following indications INCREASE, DECREASE, or REMAIN THE SAME. o. Steam Generator Level b. Steam Pressure (assume constant decay heat rate) c. Core Exit Thermocouple Temperature (**x** CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)

r-g. THEORY OF Nyg(g88_PQNEB_P(ANI_QEg88TIgN _ELUIQ@t_6NQ PAGE 4 1 ISEBUQQ1HedIGE %3-c T

v :s Qg; fo-QUESTION 5.09 (2.50) 9 c.

Define axial flux difference. (0.5) b. If delta-I is out of the programmed band to the lefti 1. Is more power being produced in the upper or lower half of the core? (0.5) 2. What manual action'should the operator, short of changing power, take to restore delta-I to the target band with rods in automatic? (0.5) c. Why does delta-I become more negative as power increases? (1.0) GUESTION 5.10 (1.00) i List two conditions necessary foi brittle fracture of a carbon steel pressure vessel to occur. I t QUESTION 5.11 (2.50) For the centrifugal pump whose operating point is. illustrated on Figure 1, perform the following: c. Illustrate on Figure 1(a) the new operating point if the pump discharge is throttled open. (0.75) b. Explain why changes in flow rate (if any) occur. (0.5) c. Illustrate on Figure 1(b) the new operating point if a second pump is started in parallel to the first. (0.75) d. Explain why changes in head loss (if any) occur. (0.5) 00ESTION 5.12 (1.00) How do the following steam parameters change (INCREASE, DECREASE, or REMAIN THE SAME) between the inlet and outlet of a real (not ideal) turbine? a. Enthalpy b. Quality i (*xxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)

D. THggBI_QE_NUgLg68_PQNgB_PL6HI_QEgB6TIQU1_ELUIggt_6NQ PAGE 5 INEBdQQXH051GS ? ~ QUESTION 5.13 (2.00) Answer the following concerning xenon: 17 ' ' a. List two methods of xenon removal. (0.5) b. Describe how and why xenon reactivity varies after a 25% power increase to 100% power (equilibrium conditions). (1.0) c. At 100% power, the reactor trips due to a mistake by an IRC technician. Criticality is planned 6 hours after the trip. If the startup is delayed for 2 hours, how and why, is the Estimated Critical Position affected? (0.5) QUESTION 5.14 (2.50) Assuming the following conditions: Assume power is 100.% Boron concentration is 600 ppm The reactor is at MOL, 5500 MWD /MTU Automatic Rod Control Initial temperature mismatch is 0 Use the curves provided to calculate how much boron must be added to initiate outward rod motion. (Your answer should be in ppm, and you must include all work and assumptions) l QUESTION 5.15 (2.00) l For the following parameters, how do they trend over core life from BOL to EOL (INCREASES, DECREASES, REMAINS THE SAME)? (Consider each separately) c. Moderator temperature coefficient (0.5) b. Excess reactivity (0.5) c. Beta bar - eff (0.5) d. Rod insertion limits (0.5) 4 (***** END OF CATEGORY 05

• • • • • )

6___ELoHI_SIEIEUE_gsEIgHt_CgNIBOL1_e8g_IggIgybgNIeIIDH PAGE 6 QUESTION 6.01 (1.50) Match the control functions with the number of controllers for VCT level control (0.5 each) ______ a. Modulate three-way valve 1. dnly one channel (LD-27) at 56% level (LIT-112 or 141) ______ b. Reset of LD-27 at 70% level 2. Both LIT-112 (decreasing) and LIT-141 ______ c. Close VCT isolation valves at 5% level QUESTION 6.02 (1.00) List the cooling medium for the following heat loads. a. Seal Water Heat Exchanger b. Diesel Generator 1A Oil Cooler

I c.

Waste Evaporator d. Turbine Gland Steam Condenser GUESTION 6.03 (1.00) Multiple Choice In refueling, when the gripper tube is supported on a fuel assembly and the weight indicator senses a reduction in the suspended weight to less than 450 lb., the ________ indicating lamp lights. a. Gripper Engaged b. Gripper Disengaged c. Tube Down d. Slack Cable i QUESTION 6.04 (1.50) List three bases for the capacity of the refueling water, storage tank per KNPP System Description 33. ,g {' (xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE *****)

~$ NN 3 Ll x o e e a d. 1 {L ,/ . i{ ] h s r ,L r x ' h__EL9HI_SIEIENE _QESIGNt_GQt.'IBQL, AND INHIBUNENIBITON PAGE _7 0 .c y. k' s QUESTION 6.05,' -; (2.00) i" P A ?. -tN7 Fill in the blanks: ~ a. Prior to head replacement, the reactor ~ b fueling cavity is. drained by pumping water from the RCS hot les to'the RWST with thev___________ pumps. (0.5) . b'. The All Volatile Treatment systen aintains proper water chemistry in the the secondary system through'the use of the chemical (0.5) 1; c. Stress corrosion cracking of austenitic stainless steel components!, in a post-LOCA environment is prevented by injection of ___________ by the _________ system. (0.5 each). s s U t n -QUESTION 6.06 (2.25) U .\\ s v For the following valves, describe' the interlock (s) and bases of each inter.lockt n s ,SI test l'ine isola, tion valves't'o the RWST (SI-208,209) (.75) a. ~ b. SI pump rebirc iscletion valbt.> (RHR-300A,B)(2 interlocks) '(1 50) g 3 i 'a QUESTION 6.07 (1kO) 1: In July cf 1981, at the Kewaunee Plant, low tedperature on a section of piping between, the BA tank.s and the S1 pun.ps was. observed.. Thi.s low temperature was caused by removal of a: piece of.. Insulation'from the boric acid heat tracing circuits to perWit maintenance on the heat tracins circuits. temperatureof'thisf1'uid}eforalowtesiperature a. What would the alar'm? (O'.5) j b. Why should the temperature be maintained above the.alani setpoint? (0.5) i1 l ~ < ,UESTION 6.08 (1.00) \\ Q What is thtj basis for the n,;tximum'pressur1Nr' spray flourate? [ \\ \\ ? r, ~ 4- ~' 1 (xxxxx CATEGORY Os CON INUED ON NEXT PAGE xxxxx) \\. i m.- ...-a.,, ,,...;.._,..,,..,_-,,.._.,,,__,,,,m, ..m._r..,, - -, _.,,, _., _ -

c. -r 41__P(6HI_SIgIgdg_QESIGHt_ggNIBQLt_6HQ_INSIBudgNI611gN PAGE 8 y k,,?:? QUESTION 6.09 (3.00) J s, Answer the following concerning a blackoutt . f. o.- Wh,at three conditions are needed to generate the blac_.kout signal? (1.2) n.- b.s List two events that occur on a safeguards power bus as a result of initiation of a blackout signal. (0.8) c. List five conditions which must be met for breaker 1-509 to close, connecting D-G 1-A to bus 1-5 during a blackout. (1.0) QUESTION 6.10 (1.50) When the Emergency Diesel Generator is started, n. At what point is the field flashed? (0.5) b.,' What two actions take place to cause the'. field to be flashed? (1.0) i i ( QUESTION 6 41 (2.25) Descr'.oe the flowpath of f.luid through the Moisture Separators. Your an se. should include the source, final destination, and components in the following flowpaths for both steams and condensates. a. Heating steam (1.00) b. Reheated steam (1.25) QUESTIkiN 6.12 (1.00) I i ( If auctioneered T-avs was high due to a failed temperature instrument, how is pressurizer level affected? f GUESTION 6.13 (2.00) Answer the following concerning the Overtemperature delta-T function: a. What is the purp~ose of the OT delta-T trip? (0.5)< b. What control action (s) are provided by the OT delta-T function? (1.0) c. Under what conditions do the(se) control action (s), occur? (0.5) (xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE xxxxx)

L. 5 s 42__ PLANT SYgIgdg_QESIQNr_CQNIRQLg_6NQ_INSIRUMENI61IDU PAGE 9 's QUESTION 6.14 (2.00) bpsi '" 4 Fill in the blanks for the. following Full Length Rod Control,qu.estions: o. Staggered stepping of the groups within banks is controlleM by the

/

n. <b. The conversion of the_ power mismatch signal to a temperature error is accomplished by the c. Loss of any one of two (+) 24 vde power supplies causes a, ___________ alarm. -d. The speed of a shutdown bank is set at ______ steps per minute. a QUESTION 6.15 ( l'. 5 0 ) Answer the following questions concerning the EHC system: e. What-',,is used for a load reference in the following' modes: 1. IMP IN (0.5), 2.! IMP OUT (0 5)'

• b.

How are valve stroke t'ines affected by pressing the CV FAST; .pushbutton? (0.5) \\,' 4 L ?

• i l

i l +a ...'a,, e l \\1 4 (xxxx*'END OF CATEGORY 06

• • • • • )

,.~ l 7. PROCEDURES - NORMAL 1_8BHgRM8(t_EME89ENgY_BN9 PAGE 10 809196991966_G9NIBQL QUESTION 7.01 (1.00) iS[iI '. ii' [. At Kewaunee, what +wo cond.itions constitute an adverse containment? ^; b QUESTIbN 7.02 (.50) Procedure A-NI-48 (Abnormal Nuclear Instrumentation) directs the use of the ceters on the front of the NIS drawers to calculate quadrant power tilt when investigating a PR UPPER OR LOWER HI FLUX DEVIATION alarm. '(True or False) QUESTION 7.03 (1.00) T, Fill in the blanks concern.ing diesel generator operation

• e.

Diesel engine temperature should be maintained at approximately ________ degr ees-F wher, not ooer ating per procedur e N-DGM-10. (0.5) b. The two hour electrical load licitation on a diesel generator is ________ KW. (0.5) l 00ESTION 7.04 (1.50) After a reactor trip, when' may the shift supervisor authorize a restart per N-ESF-5 (Three conditions) I ~ QUESTION 7.05 (1.00) ) If Secondary Integrity Criteria are not met (E-1 QRF), then procedure E-2 (Faulted Steam Generator Isolation) should be implemented. What are these two criteria? s GUESTION 7.06 (2.00) If criticality is not attained at the ECP plus 400 pear.what does the ' Reactor Startup' procedure (N-CRD-498) require the operator to do?' '(Include all options) f (***** CATEGORY 07 CONTINUED ON NEXT PAGE

• • • • • )

e Z. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11 889IQLQGIG86_99t!IB96 QUESTION 7.07 (2.00) y7 Concerning ' Emergency Boration" (E-CVC-35): a 4-e. When do you Emergency Borate? (1.0) (list four conditions) b. What immediate actions are required? (1.0) (list four actions) QUESTION 7.08 (1.50) An RCS leak occurs inside containment. List five containment parameters that have. indication or alarms that would alert the operator that the leak was in containment. QUESTION 7.09 (2.00) For the following four procedures, under what conditions in the immediate cetions must you trip the reactor? s. Continuous Rod Insertion (E-CRD-49A) b. Continuous Rod Withdrawal (E-CRD-498) c. Dropped Rod (E-CRD-49C) d. Loss of Instrument Air (E-AS-01) QUESTION 7.10 (1.50) l In procedure E-FP-08 (Fire), symptoms include control room annunciators for Fire Pump 1A and/or 1B running. j e. What two conditions cause a FIRE PUMP 1A RUNNING alarm? (1.0) b. What condition causes a FIRE PUMP 1B RUNNING alarm? (0.5) QUESTION 7.11 (1.50) While in procedure E-0 (Reactor Trip or Safety Injection), there are certain conditions for which SI must be actuated per the E-0 GRF. c. List two conditions that require Safety Injection actuation. (1.0) b. How do these conditions change with adverse conta'inment? (0.5) (xxxxx CATEGORY 07 CONTINUED ON NEXT PAGE *****)

c-m--- = 7 PRQQEQW8EE_ _Ng856(r_6ENQBMg(g_gd[BQ[NQ1_6NQ PAGE 12 BBQIQL991G86_QQNIBQL f f* 1 v' '~i' \\ QUESTION 7.12 (2.00) g ,, y -: a. State the initial conditions that must be met for starting a RCP for the following parameters per N-RC-36A: (1.5) T 1. 41 Seal delta-P. 2. CCW supply temperature. 3. VCT pressure. b. Under what conditions may the above initial conditions be omitted? (0.5) l-l QUESTION 7.13 (1.00) What procedure (s) specific' ally recommend (s) that the CSF status trees should not be implemented but be monitored for information only? QUESTION 7.14 (2.50) After working in an area for 3 hours, a worker discovers that his pocket dosimeter is off scale,and leaves the area. A survey is taken that reveals a hot area of 800 mr/hr. at 1 ft. from the hot spot. The workers activities were primarily 4 feet from the hot spot. a. Determine the exposure that the worker received. (1.5) b. If the worker's previous quarterly exposure was 826 mr', what KNPP and/or 10 CFR 20 exposure limits, if any, were exceeded? (1.0) QUESTION 7.15 (2.50) l Include all possible operator actions required in procedure FR-S.1 (Response to Nuclear Power Generation /ATWS) under the following conditions? (Each condition is considered separately.) a. Reactor has failed to trip. (1.25) b. Turbine has failed to trip. (1.25) QUESTION 7.16 (1.50) Kewaunee has experienced a low pressure in Service Water header 1A. a. What automatic actions occur when pressure reaches 72 psis (decreasing)? (1.0) b. Why does the operator hold the service water pump.' switch in the ON position for five seconds to start additional service water pumps. ( 0. () (xxxxx END OF CATEGORY 07

• • • • • )

H___eQUINIQIBoIIVE_PBQQEQQBEQi_QQMQIIIQHQt_@NQ_LIMIIGIIQHQ PAGE 13 QUESTION 8.01 (.50) el True or False C If the normal power source for an RHR pump is inoperable, then Technical Specifications requires that the RHR pump must be considered inoperable. QUESTION 8.02 (1.50) Fill in the blanks a. One diesel generator may be inoperable for a period not exceeding _____ days provided the other diesel generator is tested ________ to ensure operability... (0.5 each) b. Oxygen concentration must be maintained below ______ ppa during steady state operation. (0.5) GUESTION 8.03 (1.00) In the definition of CONTAINMNENT SYSTEM INTEGRITY, at least one door in both the personnel and the emergency airlocks is properly closed. List one administrative and one design means of insuring that this requirement is cet. (0.5 each) GUESTION 8.04 (1.00) Per KNPP Standing Night Orders, state the time limits for NRC notification required under the following conditions a. The initiation of any nuclear plant shutdown required by Technical Specifications. (0.5) ,b. An event during operation that is not covered by Kewaunee operating or emergency procedures. (0.5) (xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE

• • • • • )

._..m B___eQUINIEIB6IIVE_PBQQgQygggg_QQUQIIIgNgi_6HD_(IMII6IIQUE PAGE 14 ~ QUESTION 8.05 (1.00) d: m a Multiple. Choice }{ # n ' . +.. To protect non-ESF equipment or to warn of unusual or dang:._.erous conditions, a ______ tag is used. o. Caution b. Hold .~ c. Out of Service d. Danger QUESTION 8.06 (1.50) List two acceptable methods of performing an INDEPENDENT VERIFICATION' per ACD 1.8. I QUESTION 8.07 (1.00) e. What kind of temporary changes may be made to the refueling procedure? (0.4) , b. Who must approve the change? (List THREE) ~(0.6) DUESTION 8 08 (2.00) What does an operable SI/RHR train consist of? QUESTION 8.09 (2.00) Answer the following questions concerning Temporary Operating Procedures. c. Under what conditions may a Temporary Operating Procedure be used? (1.0) b. Prior to implementation, who may approve a Temporary Operating Procedure? (1.0) { t., .: yf '

f

(***** CATEGORY 08 CONTINUED ON NEXT PAGE

• • • • • )

8 __e9dIMISIB8IIME_PBggEQQBES _ggMDIIIQMS _6HD_LIMII6IIQHS PAGE 15 t t QUESTION 8.10 (1.50,) , l. s~ It has just been established that one pressurizer PORV'can'not'be operated from the control room. What do Technical Specifications require? (Include all options) QUESTION 8.11 (2.00) a. What is the major difference between a regular and extended Radiation Work Permit (RWP)? (1.0) , b. List the two situations that require a special RWP. (1.0) QUESTION 8.12 (1.50) With the plant at 100% power, an auxiliary operator discovered that the RWST bubbler level indicator was below the amount of water required for Technical Specifications. Later it was determined that FPC-1100 was open, ellowins a flowpath between the RWST and the Waste Holdup Tank. a. How much water do Technical Specifications require there to be in the RWST? (0.5) ,,b. What actions do Technical Specifications require the SRO to take? (1.0) _,0UESTION 8.13 (1.50) l o. For power operation at 70% power, you exceed 1 hour of time outside the target axial flux difference band in the last Y hours. What actions are required? (1.0) b. If the reactor is at 35% poker and it is planned to go to 100% power, what axial flux difference requirements must be met? (0.5) QUESTION 8.14 (1.50) An incident report is required from any supervisor recognizing an incident. ACD 2.16 defines incident situations. List six (6) of these situations. (NOTE: use general versus specific situations in your~ answer) ? I (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

1 i Sz__eQUINIgIgeIIV[_EBQQgQWR[gt_QQNQIIIQNgt_6NQ_(IMIIGIIQNE PAGE 16 [a(Nyd$,, -QUESTION 8.15 (2.50) w. Ap Answer the following Safety Limit Questions yi s t 7; a. What is the maximum limit on reactor coolant systemTpressure per Safety Limit 2.2? (0.5)

1. d.

b. What is the basis of-this Safety limit? (0.75) c. How was the limit established? (0.75) d. After shutdown of the plant for violation of this safety limit, who may authorize resumption of operation? (0.5) QUESTION 8.16 (1.50) 8. Who is the leader of the fire brigade? (0.5) b. Who are the other four members of the fire brigade? (1.0) QUESTION 8.17 (1.50) The reactor is at 95% power. A Quadrant Power Tilt Ratio (OPTR) is performed and the results show a ratio of 1.05. a. If the tilt can't be eliminated in 2 hours, what must be done? (Be specific) (0.5) +b. If the tilt condition remains for greater than 24 hours, what must ~~ be done? (0.5) ~ ( ,,c. If the GPTR was 1.10 instead with no rod misalignment, what would the ( operator be required to do? (0.5) ? II I y s ? ?, s.; e. -Q<x (xxxxx END OF CATEGORY 08 ****x) (xxxxxxxxxx*** END OF EXAMINATION xxxxxxxxxxxxxxx) + -. -

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5___IHE981_9E_HWGLEeB_E9BEB_ELeHI_9EEBBII981_ELWI9Sz_8HD PAGE 17 I6EBdQ91H8MIGH ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. w.; kU$ a ANSWER 5.01 (1.00)

• ;i.

?_' Increases. REFERENCE W Reactor Core Control, P. 6-22 ANSWER 5.02 (1.00) O. REFERENCE ~ W Reactor Core Control, p. 9-10 i ANSWER 5 03 (2.00) o. (0.4 each, 0.3 for correct order) 1. Void 2. Moderator temperature coeffient 3. Doppler power (or fuel temperature) coefficient b. More negative (0.5) REFERENCE W Reactor Core Control, p. 3-42 ANSWER 5 04 (1 50) g (0.5 each) 8. Decreases b. Decreases c. Increases REFERENCE W Thermo, Hydraulic Principles, p. 10-54, 12-4 through 12-9 W Reactor Core Control, p. 6-29 through 6-31 W t i t -, __ ~- _ _ _ _ _ _ - - . - - _ ~. _ - _., _ _.. - - _ _ _.. -___ _- _~

3 THEQBY_QE_NUGLE68_EQWEB_EL6HI_QEE86IIQHr_ELQIQ@r_6HQ PAGE 18 ISEBdQQINedIgS ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. , ' q?

• Sy.

( ANSWER 5.05 (1.00) a.; b. REFERENCE W Thermo-Hydraulic Principles, p. 10-54 ANSWER 5.06 (1 00) (0.5 each) a. Shorter b. Reactivity REFERENCE W Reactor Core Control, p. 7-35, and 4-11 ANSWER 5.07 (1.50) (Any 2 of 3 at.75 pts. each) 1. Outlet temperature of cold fluid approaches highest temperature ) of the hot fluid. _,2. More uniform temperature difference between the two fluids produces a more uniform rate of heat transfer. 3. More uniform temperature difference between the two fluids minimizes the thermal stresses throughout the heat exchanger. REFERENCE W Thermal-Hydraulic Principles,

p. 5-10 ANSWER 5.08 (1 50)

(0.5 each) 34 l' a. Increase b. Decrease f c. Increase

~ l E1__lBEQBl_9E_dQGLEAR POWER PLANT OPER8TIQH1_ELyIDS, ANQ PAGE 19 IBEBdQQldedIGE ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. ,R. , :s REFERENCE W Thermo-Hydraulic Principles, p. 14-27 e y sg ,k. ANSWER 5.09 (2.50) c. Axial flux difference is the difference between the upper and lower detector signals (0.5). (More detailed answers are also acceptable) b. (0.5 each) 1. Lower half 2. Borate c. T-cold decreases due to more steam demand from the S/Gs. This colder water enters the bottom of the core and produces more power because of the denser moderator (0.5). Therefore, delta-I decreases (0.5) (Also acceptable: T-hot is much higher than T-cold as power increases making the moderator less dense at the top so less power is produced.) REFERENCE W Reactor Core Control, p. 8-25 through 8-32 ANSWER 5.10 (1 00) (any 2 9 0.5 each) 1. Temperature Below RT-NDT 2. Material Defect or Flaw 3. External Stress on Vessel REFERENCE W Thermal.-Hydraulic Principles p. 13-60,61 ANSWER 5.11 (2 50) See Figure 1. REFERENCE W Thermo-Hydraulic Principles, pages 10-41 and 10-46 g n, N. 3

51__IBEQBY_QE_NWGLEeB_EQWEB_EleHI_QEEBoIIQHt_ELVI? a_eHQ PAGE 20 IHEBuGQIHedIGH ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. ANSWER 5.12 (1.00) (0.5 each) o. Decreases b. Decreases REFERENCE W Thermo-Hydraulic Principles, p. 7-102 through 7-110 ANSWER 5.13 (2.00) c. (0.25 pts. each) 1. Neutron absorption (burnout) 2. Decay b. Xenon reactivity initially decreases (0.25) because of increased burnout. (0.25) Production of Xe and I increases due to a higher fission rate. (0.25) This causes Xe reactivity to increase as these isotopes build up. The result is an equilibrium reached after about 40 hours at a higher xenon concentration. (0.25) c. Xenon concentration is increasins at a hi h rate, addin3 negative 3 reactivity (0.25) so the rods are at a higher position to achieve criticality. (0.25) REFERENCE I W Reactor, Core Control, p. 4-11 through 4-22 ANSWER 5.14 (2.50) Assume that a 1 5 degree F temperature mismatch causes rod motion. (0.5) (other assumptions may be accepted) -19.5 (+/- .3) from RD 6.2 (0.5) -8.95 (+/- .1) from RD 8 1 (0.5) , ppm Baron = 1 5 degrees F (-19.5 ppm /F) = 3.27 (+/- .1) ppm (1.0) ~~~I! 795"pcm/ppmI~~~~~ 8 h. REFERENCE KNpP Reactor Data Book, RD 6.2, 0.1

52__INEQBY_QE_HWGLEeB_EQWEB_EleHI_QEEBeIIQH1_ELWIQS _eNQ PAGE 21 t IHEBdQQ18851GE ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. Af .x. $ ':Ii IE , ;C. v: ANSWER 5.15 (2.00) G h t L:,: (0.5 each) c. decreases (becomes more negative) b. decreases c. decreases d. remains the same REFERENCE KNPP Reabtor Data Book, RD 3.3, 4, 8.1, 13.1 { f f ) [ 'l s v k - - - -, - -... -. - - - - -, ~,. -,,. ~., -.,. ,,.-n_

. u.e -.--.... =.:-..:.-.- . -. = -......= n &z__EL6HI_HIIIEME_DESIGHt_G9BIBQLt_eND_INEIBWHEMI6IIQN PAGE 22 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. T.S. '. ll? ANSWER 6.01 (1.50) ~ ' . ~. ']n. c. 1 b. 1 c. 2 REFERENCE KNPP System Descriptions,

p. 35-22 ANSWER 6.02 (1.00)

(0.25 each) o. CCW b. Jacket wate'r cooling system c. CCW d. Condensate REFERENCE System Descriptionsi p. 31-1, 31-2. 3-2, 2-10 i ANSWER 6.03 (1.00) } d REFERENCE KNPP System' Descriptions,

p. 53-16 ANSWER 6.04 (1 50)

(Any 3 at 0.5 each) 1. A volume suffi.cient to refill the reactor vessel above the no::les. 2. Enough borated water to maintain the core in a cold shutdown condition (with all RCCs, except the most reactive, inserted into the core) 3. Provide a sufficient volume of water on the floor to permit the initiation of recirculation. a 4. Filling the reactor refueling cavity .c REFERENCE [ KNPP System Descriptions, p. 33-5

41__PL6HI_H1HIgdH_QEgIgHt_gggIBgLt_6NQ_INSIBudgNI611gd PAGE 23 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. Dc ":' C l ?l $ 1

} s ANSWER 6.05 (2.00)

(0.5 each) V" o. RHR b. Hydrazine c. NaOH, Internal Containment Spray REFERENCE KNPP System Description, p. 34-7, 28-1 ANSWER 6.06 (2 25) a. Prevents opening sump isolation valves (SI-350A,B and SI-351A,B) when said valves are open (0.5) to prevent inadvertant release of containment vapor to the RWST (0.25) b. 1. RHR pump discharge instrument prevents said valve from opening (0.5) if pressure is above design pressure of the SI pump suction piping (alternative is to say, to protect the SI piping). (.25) 2. Said valves can not be opened unless SI-5A,B (SI pump suction valves) are shut (0.5) to prevent pumping containment sump water into the RWST with the RHR pumps. (0.25) REFERENCE KNPP System Descriptions, p. 33-9 ANSWER 6.07 (1.00) a. 150 degrees F (0.5) b. Baron would come out of solution (or insolubility of boric acid) (0.5) REFERENCE System Descriptions, p. 35-27 KNPP Technical Specifications,

p. 3 2-3 ANSWER 6.08 (1.00) a.

Prevents reaching the.operatin3 Setpoint of the air operated relief valve (0.5) durin3 a step reduction in power of 10% of full load. (0.5)

41__P(6HI_SIGIEHE_QgfIGHz_GQHIBQLg_6HQ_IN@IBUNENIGIIQH PAGE 24 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. REFERENCE ~t System Descriptions, p. 36-7 1 ,1 s ANSWER 6.09 (3.00) c. (0.4 each) 1. The'teserve auxiliary and tertiary auxiliary power sources are not available. 2. A bus voltase loss signal exists. 3. All bus power source breakers have been tripped. b. (0.4 each) 1. Load shedding 2. Blackout sequencing c. (Any five of ten at 0 2'each) 1. Reserve auxiliary and tertiary power sources unavailable 2. Breaker 1-509 in operate position 3. D-G 1-A not locked out 4. Bus 1-5 voltage loss' signal present 5. All Bus 1-5 power source breakers must be tripped 6. Breaker 1-509 selector switch in AUTO 7. Breaker 1-509 control switch not in PULL-0UT 8. D-G > 95% nominal voltage 9. D-G > 59 Hz 10. Bus 1-5 voltase low REFERENCE System Db.scriptions, p. 42:43-45 l ANSWER 6.10 (1.50) c. When the diesel generator reaches 700 rpm (0.5) g b.

1. Remove the short circuit from the field winding (0.5) 2.

Close the station battery contacter (0.5) REFERENCE HNPP System Descriptions, p. 42-20 r l o

st__PL6HI_HISI[bf_QEHIQHt_QQMIBQLt_6NQ_INEIBQUEUI611QH PAGE 25 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. i l +iZ', ANSWER 6.11 (2.25) Reheat - Main Steam HP turbine exhaust (0.25) enters the Moisture Separator where it is dryed and heated (0.25), then sent to the LP turbines (0.25). Condensate is collected and drains directly to the heater drain tank. (0.25). Heating - Main Steam (0.25) taken from the main steam lines enters the Moisture Separator to heat the HP turbine exhaust steam (0.25). This steam is condensed and drains into a reheater drain tank (RDT) (0.25) The RDT drains to provide heating to feedwater heaters 15 (A&B) (0.25) or bypass to the main condenser (0.25). REFERENCE System Description, p. 6-11, M207 i l ANSWER 6.12 (1 00) The level program controller limits reference level to 50% so cetual level would seek 50%. (1 0) REFERENCE KNPP Opetator Training Manual, p. IV-7.5 through 7 11 l ANSWER 6.13 (2.00) O. To protect against DNB. (0.5) b. Turbine Runback (0.5) ~ ' j Automatic and Manual Rod withdrawal inhibition (0.5) ( .1 if both automatic and manual not included) ) c. 5% below trip setpoint. (0.5) REFERENCE KNPP Operator Training Manual, p. IV-11.6. KNPP Technical Specifications, p. 2.3-5 ANSWER 6.14 (2.00) (0.5 each) s. Master Cycler b. Non-linear gain unit c. Non-urgent failure d. 66

42__EL6HI_SIEIENH_QESIGHt_GQUIBQLt_eHQ_IHEIBWHEMIeIIQH PAGE 26 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. REFERENCE

• i' KNPP Operator Training Manual, p.IV-3.2, 4, 10, 11 3

r. ANSWER 6.15 (1.50) o. 1. Impulse Pressure 2. Control Valve position , b. Changes the stroke time of the control valves to about 200% per minute. REFERENCE KNPP Operator Training Manual,

p. III-1.12

.6 ^f I a 11 5

Z1__EBQGEQQBEE_:.HQBdekt_6EHQBM6Lt_EMEBGENGY_eHQ PAGE 27 BeQIQLQEIGek.GQNIBQL ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. :.h'. S, af L J 4,. ANSWER 7.01 (1.00) (0 5 each) 1. Conthinment pressure greater than 4 psig 2. Containment radiation greater than IDE5 Rem /hr. REFERENCE KNPP Integrated Plant E0P, E-0 GRF ANSWER 7.02 (.50) False REFERENCE KNPP Operatins Procedure A-NI-48, p. 2. ANSWER 7.03 (1 00) c. 100 (+/-10) l b. 2950 REFERENCE KNPP Oper,atins Procedure N-DGM-10 i l ANSWER 7.04 (1.50) l (0 5 each) 1. All problems resolved. 2. Equipment malfunctions resolved. 3. Cause of the trip positively determined. REFERENCE KNPP Operating Procedure N-ESF-55, p. 2 ANSWER 7.05 (1 00) } 4 (0.5 each) 1. If ahy SG pressure is decreasing in an uncontrolled manner or 2. If any SG has completely depressurized and has not been isolated.

. -. - ~.. ~. -.. Z. PRQQEQyBEH_ _NQBdAkt_A@MQBdebt_EMESQgNQ1_ANQ PAGE 28 Be91969EIGek_GQUIB96 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. pe '.2/k., REFERENCE KNPP Emergency Operating Procedures, E-1 QRF . lp;r. 6', p ANSWER 7.06 (2 00) (0.5 each) 1. Return the rods to the ECP 2. Recalculate the ECP 3. If the ECP shows no errors, place the unit in hot shutdown 4. If errors existed and the new ECP is higher, then continue the startup. REFERENCE KNPP Operating Procedure N-CRD-49B, p.,4 ANSWER 7.07 (2.00) (0.25 each) c. 1. 'T,wo or more control rods NOT fully inserted following a reactor trip. 2. Rods stepping in below the low-low rod insertion limit. 3. An uncontrolled cooldown. 4. Unexplained reactivity increase. b. 1. Open the emergency boration line valve (CVC-440/MV-32127). 2. Start both boric acid transfer pumps in fast speed. 3. Start a second charging pump and manually adjust it to j maximum speed. 4. Open an additional 40 spm orifice isolation valve. i l REFERENCE KNPP Operating Procedures, E-CVC-35, p. 1-2 ANSWER 7.08 (1.50) (0.3 each) (any 5 of 6) 1. Containment vessel'high humidity Containment vessel high radiation or vent activitya;< 2. }', Excessive sump pump operation 3. 4. Containment high pressure 5. Containment temperature increasing 6. Containment or reactor cavity sump level high l l l

2 PRggggURgg_ _NgRMALt_Ag898dA(t_[dg8EgNQ1_ANQ PAGE 29 869IDL991G66_G9 BIB 96 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. %i f~ REFERENCE , - p >:n ' KNPP Operating Procedures, A-RC-36D, p. 1 y ' cc . s ANSWER 7.09 (2.00) (0.5 each) a. If th_e insertion continues after shifting to manual rod control. b. If the withdrawal continues after shifting to manual rod control. c. If more than one rod has dropped. d. If instrument air pressure can't'be maintained above 60 psis. REFERENCE KNPP Operating Procedures o. E-CRD-49A, p. 2 b. E-CRD-498, p. 2 c. E-CRD-49C, p. 2 d. E-AS-01, p. 1 ANSWER 7.10 (1.50) e. " Fire Pump 1A Running' means that the fire header pressure is < 110 psis (0.5) or that a deluge valve is opening. (0.5) b. " Fire Pump 1B Running

• means that fire header pressure is < 100 lbs (0.5)

REFERENCE KNPP Opetating Procedure E-FP-08, p. 1 l l ANSWER 7.11 (1.50) a. 1. RCS Subcooling based on core exit TC's < 30 F (0.5) 2. PZR level can't be maintained above 2% (0.5) b. 1. RCS subcooling changes to less than 120 F (0.25) 2. PZR level changes to more than 20% (0.25) REFERENCE KNPP Emergency Operating Procedures, E-0 GRF i i l

s s Ni Z2__P8QQgQQB[,S, _NQBt!g(1_ ggt!QBtjg(g_E!![BQ[ NGL 6,NQ PAGE 30 BeQIQLQGIGek GQt!IBQL -87/02/17-SUNDERLAND, P. ANSWERS -- KEWAUNEE e e ' \\3 (* i ' ?. 'c x f ' fa, s s 1 ig g ") N- \\ 't ANSWER 7.12* (2.00) f ~.1 7 N i o. (0.5 pts each) (' 1. 200 psid or greater ',^ 2. 105 degrees F oy less 3._ 15 psis or great,er, b. When the pump has been s+.ppped briefly'~J0.25) and it is known that thu'rehavebeen(nocharisese.adein}theservicesystems. (0.25) i s REFERENCE d c NkECy'36A s T C KNPP Opetating Procedures, r \\,N e, t- ~1 ( ANSHER' 7.13 (1.00) i s ECA-0.0, Loss of All AC Power REFERENCE it KNPP Emergency Procedures, E C A - 0,. O r,;e. 2 i. s ANSWER 7.1% f.2 50) i t c. Use inverse square law. (I-1)(D-1E2)/(D-2 E2) = I-2 [ I 800 mr/hr (1)/16 = 50 mr/hre(.75) 150 mr (.75) (30 mr/hr) (3 hrs) = _,b. Exceeded KNPP daily limit of 50 mrem / day. (1.9) REFERENCE i. d KNPP Radiation Protection Manual, p. 1 I and 0-51 g s 5 Q \\' ~ s ( k k J V = 0 l. s' 't s ...-.,,,,,--,._..,---.-s.,U.,__s,,,---.

I k '. ^ e 22__P3QQEQU853_ _NgBde(1_8ENgShebt_Edg89EHQ1_6HD PAGE 31 BeQIQL991 gel _G9 BIB 96 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P.

+ 4.

7 k'. ~

.. s ANSWEk 7.15 (2.50) i o.

Manually trip the reactor (0.5). If the reactor will not t' rip, then 1. Open the bus 1-33 and 1-43 supply breakers to deenergize the rod drive MG sets. (0.25) ( 2. Dispatch operator to locally open reactor trip breakers and Rod Drive MG set supply breakers. (0.25) 3. When the Reactor Trip breakers and the local MG set supply breakers have been opened, then reenergize Bus 1-22 and Bus 1-43 (0.25). b. Manually trip the turbine (0.5). If the turbine will not trip, then manually run back the turbine (0.25), and stop both EH oil pumps. ,s (0.25) If the turbine governor valves cannot be closed, then / manually initiate Steamline Isolation (0.25). \\ REfdRENCE KNPP Emergency Procedures, FR-S.1,

p. 2 ANSWER 7.16 (1.50)

's (Q ' J c. 1. Starts 1A1 Pump (0.33) 2. Starts 1A2 Pun.p (0.33) 3. Closes Screenhouse Header Isolation A (SW 3A/CV 31038) (0.33) b. This overrides the bearing, seal water low flow permissive. (0.5) REFERENCE \\( KNPP Oper,ating Procedure, E-SW-02, p. 1 0 f I Q ~0, o i. 4,, i s ' '.

Bi__eQUINISIB8IIVE_PBQQgQQBggg_QQNQIIIONS, ANQ_(IMIIeIIQHE t PAGE 32 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND,'P. ga' ANSWER 8.01 (.50)

$ f L 'T False.

REFERENCE KNPP Technical' Specifications, p. TS 3.7-2 ANSWER 8.02 (1 50) q o. 7, daily (0.5 each) b. .10 (0.5) REFERENCE KNPP Tech,nical Specifications, p. TS 3.1-3, 3.1-14, and 3.7-1. ANSWER 8.03 (1.00) \\- (0.5 each) o. Airlo.ck keys must be obtained from shift supervisor b. Doors are interlocked so that if one is open, the other door e is interlocked closed. I l REFERENCE l KNPP Technical Specifications,

p. TS 1.1-2a i

KNPP Operating Procedures, N-CCI-56, p. 1, 2 ANSWER 8.04 (1.00)

c. 1 br.

(0.5) b. 1 hr. (0.5) REFERENCE KNPP Standing Night Orders, ' Guidelines for NRC Immediate Notification' ,. '. + i ,c< ;, ;. ANSWER 8.05 (1.00) g,. n i# h' .d..

,e Hz__eDMINISIBoIIVE_EB9GEQWBEHI_GQHDIII9Bar_eHQ_LIMII6IIQUE PAGE 33 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. REFERENCE t, KNPP ACD 4.3, p.1 /" 7" ANSWER 8.06 (1.50) (0.75 each) 1. An qualified individual (.25) operating independently, physically verifying that a component has been placed(.25) in a specified configuration (.25), or 2. The performance of an independent functional test (0.25) without comprimising plant safety that unambiguously verifies (0.25) the component is in a specif ed condition (0.25) REFERENCE KNPP ACD 1.8r p.2 p i / ANSWER 8.07 (1.00) o. Changes that clearly do not change the engineering intent of the procedure. (0.4) b. (0.2 each) (. 1. WPS Shift Supervisor [ 2. W Refueling Coordinator 3. A sember of the plant management staff REFERENCE KNPP Refu.eling Procedures, p. 22 ANSWER 8.08 (2.00) 1. One operable SI pump (0.4) 2. One operable RHR pump (0 4)' 3. One operable RHR heat exchanger (0.4) 4. An operable flow path (0.4) capable'of taking suction on a boric acid source (0.2) and after manual transfer, taking suction from the containment sump. (0 2) REFERENCE KNPP Technical Specifications, p. TS 3.3-2

y-

Ez__eQUINI@IB8IIVE_PBQQEQQBE@t_QQUQIIIQB@i_6NQ_LIMII611QH@ PAGE 34 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. f fe, ANSWER 8.09 (2.00) c. If an operating procedure is inadequate (0.5), and the general intent of the operating procedure is not changed (0.5). b. Two members of the plant supervisory staff (0.5), at least one of which holds an SRO license (0.5). REFERENCE KNPP ACD 4.2, p. 4 '~ ANSWER 8.10 (1.50) The PORV must be restored to an operable condition within 1 hour (0.75), or the associated block valve shall be closed (0.5) and be maintained closed by administrative procedures to preverit inadvertent opening (0.25). I I REFERENCE KNPP Technical Specifications,

p. TS 3.1-2a s

ANSWER 8,11 (2.00) i. a. An extended RWP is.used for jobs of a repetitive nature (0.5). l A regular RWP is for non-repetitive jobs. (0 5) ,b. 1. Entry into any area posted as a Radiation Hazard Area. (0.5) 2. Maintenance on any component that has a contact radiation reading of greater than 1R/hr. (0.5) REFERENCE KNPP ACD 6.3, p. 1, 2 ANSWER 8.12 (1.50) a. 272,500 gallons (0.5) b. If not restored within 1 hour (0.5), he must initiate action in one hour to shut the plant down to Hot Standby. (0 5)' ne. ~ REFERENCE KNPP Tech.nical Specifications, p. TS 3.3-3 Nuclear Power Experience, Vol., PWR-2, VIII Auxiliary Systems, p. 175

Dz__eQUINISIBoIIVE_PBQQEQQBEli_QQNQIIIQUEl_6HQ_kIdII611QUE PAGE 35 ANSWERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. y? Y i a[.h 7w ANSWER 8.13 (1.50) c, ' a. 1. Reduce power below 50%. (0.5) 2. High neutron flux setpoint reduced to less than or equal to 55% of rated power. (0.5) b. Axial Flux Difference must not be out of the target band for more than two hours of the previous 24 hours. (0.5) REFERENCE KNPP Technical Specifications, p. TS 3.10-4 and 4a ANSWER 8.14 (1.50) (Any 6 of 8) (0.25 each) 1. Failure of safety related equipment '2. Theft or loss of licensed material 3. Overexposure and/or excessive levels and concentrations 4. Defect.or noncompliance 5. Exceeding a Technical Specification safety limit or LCO 6. Immediate notification 7. Reportable event 8. Security event REFERENCE KNPP ACD 2.16, p. 1 ANSWER 8.15 (2.50) a. 2735 psis b. Prevents' radionuclides contained in the RCS from reaching the atmosphere. (Also acceptable is to maintain RCS integrity) c. Max transient pressure allowable in the pressure vessel in ASME Codes is 110% of design pressure. l d. NRC REFERENCE KNPP Technical Specifications, p. TS 2.2-1 h" r 2 t b.- I' b l l

H___6DMINISIB8IIMg_PBQQ[QQBES _QQNQIIIQHS _6HQ_blMII6119HQ PAGE 36 t I AW9%ERS -- KEWAUNEE -87/02/17-SUNDERLAND, P. -s.

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ANSWER 8.16 (1 50) , ? T: - cu + 4 i g s. Auxiliary Operator (0.5) ~ jit-b. 1. Equipment Operator (0.25) 2. Radiation Protection Technologist (0.25) 3. Two Contract Security Personnel (0.25 each) REFERENCE KNPP ACD 14.1, p. 4 ANSWER 8.17 (1.50) s a. Restrict maximum power level two percent for every one percent tilt ratio over 1.0, so maximum power is reduced by 10% to 90%. (0.5) b. Reduce power to 50% or lower. (0.5) c. Reduce reactor power to the No Load Condition (5% power or less) (0.5) REFERENCE KNPP Technical Specifications, p. 3.10-5 l l i.vf +s s

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X. MASTER COP _Y U. S. NUCLEAR REGULATORY C0194ISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: KEWAUNEE REACTOR TYPE: PWR-WEC2 DATE ADMINISTERED: 87/02/17 EXAMINER: VICTOR, F. CANDIDATE: INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one 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 (6) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.00 25.00 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 25.00 25.00 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS r 25.00 25.00 3. INSTRUMENTS AND CONTROLS 25.00 25.00 4. PROCEDURES - NORMAL, ABNORMAL, j EMERGENCY AND RADIOLOGICAL CONTROL 100.00 Totals l Final Grade 1 All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature I

es',4. NRC RULES AND GilIDELINES 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 only 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 each section of the answer sheet. 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only on one 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 three 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 ia 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 examiner 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.

,i ~

18. When you couplete 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. 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

' **l' PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW t QUESTION 1.01 (1.00) Determine the temperature of the fluid just downstream of a pressurizer PORY which is partially stuck open at normal operating pressure if the back pressure in the pipe just downstream of the PORY is 85 psig. State whether the fluid will be subcooled, saturated or superheated. QUESTION 1.02 (2.00) With the plant operating at 85 percent power, control systems in automatic, how will the following changes in plant conditions affect DNBR (Increase, Decrease, or No Change). Consider each case separately. 1. The operator manually withdraws control rods 30 steps without changing turbine load. (0.5) l 2. The first group of condenser steam dump valves fail open. (0.5) 1

3. - Raise the setpoint on the pressurizer pressure controller by 30 psig.

(0.5) 4. Reactor coolant flow decreases by 10% (no reactor trip). (0.5) f QUESTION 1.03 (2.00) I State the type of device used to measure flow rate in the Reactor l Coolant system and describe the principle of operation. QUESTION 1.04 (2.00) How does the Available Net Positive Suction Head for a centrifugal pump change (Increase, Decrease or Remain The Same) given the following conditions? EXPLAIN why. Consider each separately.

a. The height difference between the pump and the tank supplying the pump suction is reduced.

(1.0)

b. The fluid upstream of the pump is cooled.

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

• l '. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3

THERMDDYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.05 (2.00) An estimated critical position (ECP) has been calculated for a reactor startup that is to be performed 6 hours after a trip from a 60 day full power run. How would each of the following events or conditions (independently) affect the actual critical rod position compared to the ECP? In your answer, state whether the actual rod position would be: Higher than ECP, Lower than ECP, or No significant difference.

a. The startup is delayed for approximately two hours (0.5)

b. The steam dump pressure setpoint is increased by 100 psi above the no-load setpoint.

(0.5)

c. A new boron sample shows a boron concentration 20 ppm higher than that used in the ECP calculation.

(0.5) 4

d. All Steam Generator levels were raised by 5% just prior to criticality.

(0.5) QUESTION 1.06 (2.00) Doppler power coefficient changes from beginning of life to end of life because of four factors. List the FOUR factors and state which factor is most dominant? (2.0) QUESTION 1.07 (1.00) The reactor is subcritical with D-Bank at 78 steps. It has been determined that 250 pcm are needed to reach criticality and be on an acceptable ramp toward 10E-8 amps. Use the attached curve (s) to determine the required bank position. Assume no change in boron concentration or xenon. Briefly EXPLAIN how you arrived at your answer. QUESTION 1.08 (1.00) The reactor is initially at 4 x 10E-9 amps. Positive reactivity is inserted to put the reactor on a constant SUR of 0.25 DPM. Determine how long it takes to reach 1.4 x 10E-8 amps. (Show work) 1 (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

• l'.

PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4 THERF0 DYNAMICS, HEAT TRANSFER AND FLUID FLOW 4 QUESTION 1.09 (1.50) a. With RCS Tave equal to 290 degrees Fahrenheit, what is the maximum allowable RCS pressure in psig which does not violate the 320 degree Fahrenheit differential temperature limitation between the RCS and the pressurizer? (0.75) b. What steam generator pressure must be established to ensure a 50 degree Fahrenheit subcooling margin when RCS pressure is 1000 psig? (0.75) QUESTION 1.10 (1.50) A reactor plant is operating at 100% power with RCS Tave at 562 F and a steam pressure of 735 psig. What is the new value for Tave to maintain 100% power and a steam pressure of 735 psig with 10% of the steam generator tubes plugged (assume no change in RCS mass flow rate). SHOW ALL WORK, ] including any applicable formulas. QUESTION 1.11 (1.50) i Explain HOW and WHY Control Rod Worth is affected by a 15 degree F increase in Tave. QUESTION 1.12 (2.50) a. List the THREE most significant reactivity coefficients in order of j INCREASING contribution to total power coefficient at BOL. (1.5) b. How does total power coefficient vary as the core ages? (1.0) (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

• *
• l '. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 5

THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.13 (2.50)

a. State the TWO methods of Xenon production and the TWO methods of removal.

(1.0)

b. State the method of Samarium production and removal.

(0.5)

c. Compare Xenon and Samarium in regard to their variation in concentration following a power reduction from 100% to 50% and remaining at 50% for two weeks.

(1.0) QUESTION 1.14 (2.50)

a. Define Shutdown Margin (SDM) per Technical Specification.

(1.0)

b. State / List THREE reasons for Rod Insertion Limits per Technical Specification.

(1.5) (***** END OF CATEGORY 01 *****)

' '

• 2'.

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 6 i QUESiION 2.01 (1.50) Describe THREE possible flowpaths from the boric acid storage tanks to the charging pumps that could be used for boration. Include major valves and components. QUESTION 2.02 (1.50)

a. Explain why each of the following substance (s) is added to the Chemical and Volume Control System.

1. Hydrogen gas 2. Hydrazine 3. Lithium hydroxide 4. Nitrogen gas (1.0)

b. Describe how the contents of the Chemical Mixing Tank are transferred to the RCS system including flow path and how flow rate is controlled?

(0.5) QUESTION 2.03 (2.00) TRUE or FALSE.

a. When the control switch for Small-capacity Station and Instrument Air i

Compressor 1A is placed in the "AUT0" mode, the compressor will start and stop as required to maintain 90 psig siminum and 105 psig maximum receiver air pressure. (0.5)

b. Station air supplied to the inside of containment is isolated during Reactor Operations.

(0.5)

c. Automatic control valves will isolate the Station Air header when pressure in the Station and Instrument air header decreases to 85 psig.

(0.5)

d. Small-capacity Air Compressor 1C is the only small capacity air compressor that can be controlled at the compressors local panel. (0.5)

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

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• 2'.

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 7 QUESTION 2.04 (2.50) What system (s) provide normal cooling for the following: (a) SI pumps seals. (0.5) (b) Boric acid evaporator. (0.5) (c) Spent fuel pit heat exchanger. (0.5) (d) Charging pumps. (0.5) (e) Pressurizer relief tank. (0.5) QUESTION 2.05 (1.50)

a. What THREE accidents form the design basis for the Safety Injection System?

(0.75)

b. Why are the Safety Injection lines into the reactor vessel normally valved closed?

(0.75) QUESTION 2.06 (1.50) List THREE signals that will automatically close either an individual or both main steamline isolation valve (s). Specify if an individual valve or both valves close for each signal. (1.5) QUESTION 2.07 (2.50)

a. Describe the flow paths by which the 118 VAC Instrument Bus No.IY is powered from MCC 1-52C 480 VAC bus. List all major components and include their NORMAL (preferred) and STANDBY (alternate) power sources where they exist. (Sketch acceptable.)

(2.0)

b. What PREVENTS energizing Instrument Bus IV from both the normal and stand-by power supplies at the same time?

(0.5) (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

a. ' ' 2 '. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8 l QUESTION 2.08 (2.50)

a. List THREE functions of the Auxiliary Feedwater pump (s) recirculation system.

(1.5)

b. If the suction for the Auxiliary Feedwater pumps had been shifted to the Service Water System and SW Train A is isolated explain how this casualty would affect the operation of the Auxiliary Feedwater System.

(1.0) QUESTION 2.09 (1.50)

a. List THREE sources capable of supplying water to the suction of the High Head Safety Injection Pumps and state which source is used first on receipt of a Safety Injection signal. (All components function normally. )

(1.0)

b. Describe the feature which has been designed into the Safety Injection System to minimize the probability of a ruptured injection line causing a loss-of-coolant accident.

(0.5) QUESTION 2.10 (2.50)

a. One of the pre-start interlocks that will prevent the Emergency Diesel Generator from starting is a STOP LOCK 0UT condition. List FOUR conditions that will initiate a STOP LOCK 0UT.

(Setpoints not required.) (2.0) TRUE or FALSE

b. When power is lost to ESF bus 1-6 the bus goes into a Power Source Search Mode which will check the Tertiary Auxiliary Transformer first, then the Reserve Auxiliary Transformer and finally the Emergency Diesel Generator 1B as a source of power.

(0.5) l QUESTION 2.11 (1.50)

a. Describe how the signal that automatically activates the Contaiment Spray System is DEVELOPED including setpoints and coincidence.

(1.25)

b. How are the spray ring headers inside containment tested to demonstrate i

that the nozzles are not clogged? (0.25) j (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****) I..

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 1 QUESTION 2.12 (1.00) Describe the operation of the INTERLOCK associated with a Main Steam Isolation valve closure. QUESTION 2.13 (1.50)

a. What design feature will minimize the affect of loss of $$N-air t

on the operation of the Pressurizer Power Operated Relief Valves (PORVs) (1.0)

b. What is the basis for the design capacity of the Pressurizer Relief Tank rupture disk?

(0.5) QUESTION 2.14 (1.50)

a. List the NORMAL and the EMERGENCY source of makeup water for the Component Cooling Water System.

(0.5)

b. List the power source (s) (bus) for the Component Cooling Water pump motors.

(1.0) t i l (***** END OF CATEGORY 02 *****)

3'. INSTRUENTS AND CONTROLS PAGE 10 QUESTION 3.01 (2.50) Answer the following questions regarding the Main Feedwater and Condensate systems:

a. What automatic actions will occur in response to a low feedwater pump suction pressure condition?

(0.75)

b. List FOUR permissives that must be satisfied before a Feedwater Pump will start.

(1.0)

c. List the automatic actions that occur when a Feedwater Pump trips and state which system component supplies the actuation signal.(0.75)

QUESTION 3.02 (2.00)

a. List FIVE Equipments / Components associated with Rod Control that are RESET by the Control Board Startup Pushbutton.

(1.5)

b. Explain how Rod Control Operation is affected by a R0D CONTROL URGENT ALARM at power.

(0.5) QUESTION 3.03 (1.50) Indicate if the following statements concerning Source Range Instrumentation are TRUE or FALSE:

a. The Source Range audio count rate can be changed by a power of ten, hundred, thousand, or ten thousand. Changing the audio count rate does not affect the count rate for the visual display.

(0.5)

b. If the Containment Evacuation Alarm is manually blocked, the High Flux at Shutdown Alarm is not affected.

(0.5)

c. The level amplifier provides signal input for the High Flux at

.l Shutdown Alarm and the Visual-Audio Count Rate Channel. (0.5) i QUESTION 3.04 (1.75) The reactor is critical at 5% rated thermal power during a normal reactor startup. List ALL reactor trips which are DISABLED in this condition. QUESTION 3.05 (2.00) The Volume Control Tank (VCT) level instrumentation, in addition to providing Control Room Indication and Alarms, initiates control signals at various levels in the VCT. List FOUR control signals including the levels at which they occur. (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

l *3-INSTRUMENTS AND CONTROLS PAGE 11 QUESTION 3.06 (2.50) List FIVE control interlocks, INCLUDING coincidence, that will stop automatic rod withdrawal. QUESTION 3.07 (1.00) Explain how the feedwater THREE ELEMENT CONTROLLER compensates for the affect of " shrink" and " swell". QUESTION 3.08 (2.50) The plant is operatihg at 80 percent power with all systems in automatic when CHANNEL III (controlling) pressurizer pressure channel FAILS HIGH.

a. List all the IMMEDIATE AUTOMATIC actions which occur because of the failure. Alarms are not required. Assume no operator action.

(1.5)

b. After completing all required operator actions, the plant is stabilized at the previously existing conditions with an alternate pressurizer pressure channel selected for control and the FAILED INSTRUMENT BISTABLE tripped. At this time, the CHANNEL I Tcold instrument FAILS LOW. List the immediate automatic action (s) which occur (s) as a result of this additional failure.

(Assume no operator action.) (1.0) QUESTION 3.09 (2.00)

a. List the THREE conditions that will cause an AUTOMATIC start of the Emergency Diesel Generator.

(Normal system lineup.) (1.5)

b. If the first AUTOMATIC start attempt is unsuccessful, HOW MANY ADDITIONAL starting attempts will be made before the engine start signal is LOCKED OUT?

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

~..-...

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• 3'. INSTRUMENTS AND CONTROLS PAGE 12 QUESTION 3.10 (3.00)

The plant is operating at 50% power with all control systems in automatic. Bank D rods are at 150 steps. Given the following conditions / situations, describe the INITIAL rod motion which occurs. Your answer should contain IN, OUT, or NO MOTION with a brief explanation. Assume no operator action (unless stated) and the reactor does NOT trip. Consider each case separately.

a. B steam generator MSIV inadvertantly closes (turbine load constant).

b. Loop A narrow-range Thot instrument fails high.

c. Loop B narrow-range Tcold instrument fail low.

d. Turbine load is ramped to 20% at 5% per minute (0.75 for each)

QUESTION 3.11 (1.50)

a. List TWO conditions which satisfy the C-9 permissive circuit for the Condenser Steam Dump System.

Include setpoints. (1.0)

b. List the Mode Selector Switch position (s) which provide a full trip _

open feature for the Steam Dump Valves. (0.5) QUESTION 3.12 (1.50) List THREE of the four signals that will automatically start the Control Room Post-Accident Recirculation fans when the control room switch is in p AUTO. l QUESTION 3.13 (1.25) Protective devices associated with the mair. transformers, main auxiliary transformers, and various power distribution buses, all function to trip lockout relays 86/TIA and 86/T1B. List FIVE safety / protective actions that occur when lockout relays 86/TIA and 86/T1B are tripped. 1 i (***** END OF CATEGORY 03 *****)

' ' 4 *. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 13 RADIOLOGICAL CONTROL QUESTION 4.01 (2.00) The plant undergoes a turbine trip from 100% power and the R0 notes that an automatic trip did not occur nor can the reactor be tripped manually..

a. What procedures are referred to in this situation?

(0.5) i i

b. What is the next operator action per procedure following the failure of a manual reactor trip initiation and WHAT does this action accomplish?

(0.5) QUESTION 4.02 (1.50) You have indication that instrument air pressure is dropping (not a meter problem) and is at 80 psig but the service air header isolation valve is i still open and the backup air compressors have not started. I

a. What is the cause of the low instrument air pressure?

(0.5)

b. E-AS-01, " Loss of Instrument Air," requires a manual reactor trip if instrument air decreases to what pressure? Why is this action necessary?

(1.0) QUESTION 4.03 (1.50) Indicate if the following statements are TRUE or FALSE.

a. According to A-MI-87, " Miscellaneous Instrumentation Abnormal Operation", a licensed Reactor Operator may trip reactor protection bistables with permission of the Shift Supervisor, if a qualified l

I&C man is not immediately available. (0.5)

b. If the Loose Parts Monitoring System (LPMS) confirms the existance of a valid HIGH alarm, operating procedures require that the operator trip the: reactor and then evaluate the cause of the alarm.

(0.5)

c. According to E-FP-08, " Emergency Operating Procedure-Fire", the Plant Emergency Alarm is not sounded until a Plant Operator (does not have to be licensed) at the scene provides a verbal evaluation or report. (0.5)

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

' ' ~ 4'. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14 RADIOLOGICAL CONTROL QUESTION 4.04 (2.50) The following concern statements listed in N-0-01 " Plant Startup from Cold Shutdown Conditions to Hot Shutdown Conditions". a. The shutdown banks must be fully withdrawn whenever positive reactivity is being added by Boron or Xenon changes, RCS temperature changes or control bank movement except during 2 conditions. State the TWO conditions. (1.0) b. Explain why pressurizer pressure is held in the 1800 to 1900 psig range until Steam Generator pressure is >600 psig? (1.5) QUESTION 4.05 (2.50) Briefly describe the automatic actions that occur (if any) when the following Radiation Monitoring System channels reach their alarm setpoints:

a. Steam Generator Sample Monitor (R-19A)

(1.5)

b. Component Ccoling Water System Liquid Monitor (R-17)

(0.5)

c. Service Water Monitor (R-20)

(0.5) QUESTION 4.06 (2.50) State the FOUR Immediate Operator Actions listed in ECA-0.0, " Loss of ALL i AC Power". INCLUDE how these actions are verified. NOTE: Sub steps are required. QUESTION 4.07 (2.00) State the TWO conditions per step 1 of Operating Procedure E-1 " Loss of Reactor or Secondary Coolant" which would require the operator to stop the RCPs. (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

I

• 4.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15 RADIOLOGICAL CONTROL l QUESTION 4.08 (1.50) List FIVE examples or general statements of the kind of significant operations or actions that the Reactor Operator will enter in the Reactor Log per administrative directives. Omit data filled in on stamped form at the beginning of each day. (1.5) QUESTION 4.09 (2.50)

a. List TWO of the four heat sinks (different components) listed in Technical Specification which must be operable whenever the average reactor coolant temperature is less than or equal to 350 degrees F but greater than 200 degrees F.

(1.0) l

b. State the required action (s) according to Technical Specification when i

ONE of the Pressurizer PORV's becomes inoperable during hot standby and/or operating modes. (1.5) QUESTION 4.10 (1.50) According to STANDING NIGHT ORDERS list THREE of the seven parameters or factors that should be considered when determining whether an actual rod misalignment exists or an electrical problem with Individual Rod Position Indication (IRPI) problem exists. QUESTION 4.11 (2.50) According to A-RHR-34, " Loss of Residual Heat Removal Cooling", what action will occur when a RHR pipe ruptures in the RHR pump pit. List the AUTOMATIC action (s) and FOUR Operator IP9EDIATE actions. QUESTION 4.12 (1.50) List THREE symptoms of inadvertent boron dilution in accordance with A-RC-36F, " Inadvertent Boron Dilution while at Hot or Cold Shutdown". i (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) j i ..r_,r-

v

..____.-,,,-,m-_..-..-z-.--._-._-___,-_...____m,__.-

= 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL l l QUESTION 4.13 (1.00)

a. List the THREE people by title or job description who a st sign a Regular RWP prior to anyone starting work specified on the permit.

(0.75)

b. You are required to periodically check your self reading pocket dosimeter (SRD) while in a RCA. What " reading" would require you leave the area immediately and notify HP personnel, according t3 KEWAUNEE " Radiation Protection Training Manual".

(0.25) i (***** END OF CATEGORY 04 *****) (************* END OF EXAMINATION ***************)

p +*. ' ' - EQUATION SHEET ~ C

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Cycle efficiency = Net Work (out) v = ag a = v,t + at Energy (in) E = aC a = (vg - v )/t 9 KE = 1uv A = AN g vg = v, + at A = A,e PE = agh a = 8/t A = In 2/tg = 0.693/tg W = v&P t (eff) = (t, )(t ) s g AE = 931Am ( + ) Q=[nCAT -IX P I.Ie o Q = UAAT I - I. UX Pur = W a -X/ M g I1 10 9 SUR(t) P=P 10 TVI. = 1.3/u p.p.t/T HYL = 0.693/u o SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg)' /A*gr ) o SUR = 26 g, CR, = S/(1 - K,gf ) j CR (1 - K,gg)g = CR (I - Keff)2 T = '(1*/p ) + [(6 - p)/A,gg ] ~ ' y 2 p 7. g*f (, _ y, M = 1/(1 - Kegg) = CR /CR g 0 T = (3 - p)/ A,ggo g, gg,g ff)0 (I - Eeff}l p = (K,gg-l M K,gg = R,gg/Kaff SDM = (1 - K,gg)/K,gg [1*/TKyff ] + [B/(1 + A,gg )] t* = 1 x 10 seconds -3 a= T P = I(V/(3 x 10 ) A,gg = 0.1 seconds" t = Na Idgg=Id22 WATER PARAMETERS Id =Id g 2 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters) I gal. = 3.78 liters R/hr = 6 CE/d (feet) I ft = 7.48 gal. MISCELLANEOUS CONVERSIONS 3 Density = 62.4 lbm/ft 1 Curie = 3.7 x 1010dps Density = 1 gm/cm I kg = 2.21 lba Heat of va;orization = 970 Itu/lba 1 hp = 2.54 x 103 BTU /hr Heat of fusica = 144 Btu /lba 1 Hw = 3.41 x 10 Beu/hr ,k 1 Atm = 14,7 psi - 29.9 in. Fg. I Btu = 778 ft-lbf I ft. H 0 = 0.433~, Ibf/in 1 inch = 2.54 cm y F = 9/5 C + 32 "C = 5/9 ( F - 32)

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i 1 4 I ~ I J Table 1. Saturated Steam: Temperature Table I Abs Press. Specific Volume Enthalpy Entropy ] Temp lbper Sat. Sat. Sat. Sat. Sat. Sat. Temp Fahr SqIn. Liquid Evap Vapor Li uid Evap Vapor Liquid Evap Vapor Fahr hg h se sig s t f g g t p vg vgg vg g i 32 0 0 08859 0.016022 3304.7 3304.7 0.0179 1075.5 1075.5 0.0000 2.1873 2.1873 32.0 l 34.8 0 09600 0 016021 3061.9 3061.9 1.996 1074.4 1076.4 0 0041 2.1762 2.1802 34.8 1 36 0 0.10395 0.016020 2839.0 2839 0 4.008 1073.2 1077.2 0.0081 2.1651 2.1732 35.0 38.0 0.11249 0.016019 2634.1 2634.2 6.018 1072.1 1078.1 0.0122 2.1541 2.1663 38.8 f 48 8 1.12163 0.016019 2445.8 2445.8 8.027 1071.0 1079 0 0.0162 2.1432 2.1594 40.0 t 42.0 0.13143 0.016019 2272.4 2272.4 10 035 1069 8 1079.9 0 0202 2.1325 2.1527 42.0 i 44 8 0.14192 0.016019 2112.8 2112.8 12.041 1068.7 1080.7 0.0242 2.1217 2.1459 44.0 4E I 0.15314 0.016020 1965.7 1%5.7 14.047 1067.6 1081.6 0 0282 2.1111 2.1393 45.0 48.I 0.16514 0.016021 1830.0 1830.0 16.051 1066.4 1082.5 0.0321 2.1006 2.1321 .48.8 j I $0.8 0.17796 0.016023 1704.8 1704.8 18.054 10653 1083.4 0.0361 2.0901 2.1262 50.9 52.0 0.19165 0.016024 1589.2 1589.2 20.057 1064.2 1084.2 0.0400 2.0798 2.1197 52.0 2 54.8 0.20625 0.016026 1482.4 1482.4 22.058 1063.1 1085.1 0.0439 2.0695 2.1134 54.0 56.8 0.22183 0.016028 1383.6 1383.6 24.059 1061.9 1086.0 0.0478 2.0593 2.1070 56.8 58.I 0.23843 0.016031 1292.2 1292.2 26.060 1060.8 1086.9 0.0516 2.0491 2.1008 58.0 g $0.8 0.25611 0.016033 1207.6 1207.6 28.060 1059.7 1087.7 0.0555 2.0391 2.0946 00.0 52.8 0.27494 0.016036 1129.2 1129.2 30.059 1058.5 1088.6 0.0593 2.0291 2.0885 52.0 i Gil 0 29497 0.016039 1056.5 1056.5 32.058 1057.4 1089.5 0.0632 2.0192 2.0824 54.0 $6.5 0 31626 0 016043 989.0 989.1 34.056 10563 1090.4 0.0670 2.0094 2.0764 EE.8 l 88.5 0.33889 0.016046 926.5 926.5 36.054 1055.2 1091.2 0.0708 1.9996 2.0704 68.8 70.0 0.36292 0.016050 868.3 868.4 38.052 1054.0 1092.1 0.0745 1.9900 2.0645 ft.I i 12 0 0 38844 0.016054 8143 814.3 40.049 1052.9 1093.0 0.0783 1.9804 2.0587 72.8 74.8 041550 0.016058 764.1 764.1 42.046 1051.8 1093.8 0.0821 1.9708 2.0529 74.8 75.0 0.44420 0.016063 717.4 717.4 44.043 1050.7 1094.7 0.0858 1.%I4 2.0472 75.0 78.8 0.47461 0.016067 673.8 673.9 46.040 1049.5 1095.6 0.0895 1.9520 2.0415 78.0 i 88.8 0 50683 0.016072 6333 633.3 48.037 1048.4 1096.4 0.0932 1.9426 2.0959 88.0 l 82.5 0 54093 0.016077 595.5 595.5 50.033 10473 10973 0.0969 1.9334 2.0303 82.0 i 84.8 0.57702 0 016082 560 3 560.3 52.029 1046.1 1098.2 0.1006 1:9242 2 0248 84.0 SE 8 0 61518 0 016087 227.5 527.5 54.026 1045.0 1099 0 0.1043 1.9151 2.0193 85.0 ) 88 8 0 65551 0.016093 4%.8 4%.8 56.022 1043.9 1099.9 0.1079 1.9060 2.0139 88.0 i 90.5 0 69813 0016099 468.1 468.1 58 018 1042.7 1100.8 0.1115 1.8970 2.0086 90.8 l 92 0 0.74313 0.016105 441.3 4413 60 014 1041.6 1101 6 0.1152 1.8881 2 0033 92.8 j 94.8 079062 0.016111 4163 416.3 62.010 1040.5 1102 5 01188 1.8792 1.9980 94 I l 95 5 034072 0 016117 392.8 392.9 64.006 1039 3 1103 3 0 1224 1.8704 1.9928 SEI 38.0 0 89356 0 016123 370.9 370.9 66 003 1038 2 1104 2 01260 1.8617 1.9876 38 8 l

Abs Press. Specific Volume Enihalpy Entropy Temp Lb per Sat. Sat. Sat. Sat. Sat. Sal. Temp Fahr Sq in. Liquid Evap Vapor I.iquid Evap Vapor Liquid Evap Vapor Fahr t p vg vgg vg hg h ig hg sg sig s i g 180.8 0.94924 0.016130 350.4 350.4 67.999 1037.1 1105.1 0.1295 1.8530 1.9825 100.0 II2.I 100789 0.016137 331.1 331.1 69.995 1035.9 1105.9 0.1331 1.8444 1.9775 182.8 184.5 1.06 % 5 0.016144 313.1 313.1 71.992 1034.8 1106.8 0.1366 1.8358 1.9725 IN.O 1 IDE O 1.1347 0 016151 296.16 296.18 73.99 1033 6 1107.6 0.1402 1.8273 I.9675 188.8 I let S 1.2030 0.016158 280.28 28030 75.98 1032.5 1103.5 0.1437 1.8188 19626 188.0 { 118 8 1.2750 0 016165 26537 26539 77.98 1031.4 11093 0.1472 1.8105 1.9577 110.0 112.8 1.3505 0 016173 25137 25138 79.98 1030.2 1110.2 0.1507 1.8021 1.9528 112.0 1148 1.4299 0016180 238.21 238.22 81.97 1029.1 1111.0 0.1542 1.7938 1.9480 114.8 118 8 1.5133 0 016188 225 84 225.85 83.97 1027.9 1111.9 0.1577 1.7856 1.9433 116.0 118.0 1.6009 0.016196 214.79 214.21 85.97 1026.8 1112.7 0.1611 1.7774 1.9386 118.0 128 I 1.6927 0.016204 203.25 203.26 87.97 1025.6-1111.6 0.1646 1.7693 1.9339 120.0 122.8 1.7891 0 016213 192.94 192.95 89.% 1024.5 1114.4 0.1680 1.7613' l.9293 122.8 1248 1.8901 0 016221 183 23 183.24 91 96 1023.3 11153 0.1715 1.7533 1.9247 124.0 126.8 1.9959 0.016229 174 08 174.09 93.% 1022.2 1116.1 0.1749 1.7453 1.9202 125.0 121 8 2.1068 0 016238 165.45 165.47 95.% 1021.0 1117.0 0.1783 1.7374 1.9157 128.8 130.0 2.2230 0 016247 15732 15733 97.96 1019.8 1117.8 0.1817 1.7295 1.9112 130.0 132.8 2.3445 0 016256 149 64 149.66 99.95 1018.7 1118.6 0.1851 1.7217 1.9068 132.0 i 134.0 2.4717 0 016265 142.40 142.41 101.95 1017.5 1119.5 0.1884 1.7140 1.9024 134.I 1 136.8 2.6047 0 016274 135.55 135.57 103.95 1016.4 1120 3 0.1918 1.7063 1.8980 136.0 13I O 2.7438 0 016284 129.09 129.11 105.95 1015.2 1121.1 0.1951 1.6986 1.8937 138.0 148 O 2.8892 0 016293 122.98 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 140.0 l 142 O 3.0411 0.016303 117.21 117.22 109.95 1012.9 1122.8 0.2018 1.6534 1.8852 142.5 144.0 3.1997 0 016312 111.74 111.76 111.95 1011.7 1123.6 0.2051 1.6759 1.8810 144.0 146.0 3.3653 0 016322 106.58 106.59 113.95 1010.5 1124.5 0.2084 1.6684 1.8769 148.I 148.0 3.5381 0.016332 101.68 101.70 115.95 1009.3 1125.3 0.2117 1.6610 1.8727 148.8 1 158 8 3.7184 0.016343 97.05 97.07 117.95 1008.2. 1126.1 0.2150 1.6536 1.8686 150.0 1525 3.9065 0 016353 92.66 92.68 119.95 1007.0 1126.9 0.2183 1.6463 1.8646 152.0 154.8 4.1025 0 016363 88.50 88.52 121.95 1005.8 1127.7 0.2216 1.6390 1.8606 154.0 155.8 4 3068 0 016374 84.56 84.57 123.95 1004.6 1128.6 0.2248 1.6318 1.8566 156.8 158.8 4 5197 0.016384 80.82 80.83 125.96 1003.4 1129.4 0.2281 1.6245 1.8526 158.0 168 0 4.7414 0 016395 77.27 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 168.5 162.0 4 9722 0 016406 73.90 73.92 129.96 1001.0 1131.0 0.2345 1.6103 1.8448 162.8 1640 52124 0 016417 70.70 70.72 131.96 999.8 1131.8 0.2377 1.6032 1.8409 154.8 166 9 5 4623 0 016428 67.67 67.68 133.97 998.6 1132.6 0.2409 1.5%1 1.8371 158.I l 1680 5 7223 0.016440 64.78 64.80 - 135.97 997.4 1133.4 0.2441 1.5892 1.8333 158.8 170 0 5.9926 0 016451 62 04 62.06 137.97 9%.2 1134.2 0.2473 1.5822 1.8295 170.0 172.0 6 2736 0016463 59 43 59.45 139.98 9950 1135 0 0.2505 1.5753 1.8258 172.0 1740 6 5656 0 016474 56.95 56.97 141.98, 993.8 1135.8 0 2537 1.5684 1.8221 174.8 176 0 6 8690 0 016486 54.59 54 61 143.99 992.6 1136.6 0.2568 1.5616 1.8184 176.I 18 0 7.1840 0 016498 5235 5236 5 99 991.4 !!37.4 0 2600 1.5548 1.8147 '8

i 5 i 9 i 1 j i Abs Press. Specific Volume Enthalpy Entropy Temp I.b per Sat. Sat. Sat. Sat. Sat. Sat. Temp j 3 Fahr SqIn. Liquid Evap Vapor Liquid Evap Vapor Liquid Evap Vapor Fahr t p v, v tg vg hg h fg h sg sgg sg i g ~ 180.0 7.5110 0.016510 50.21 50.22 148 00 990.2 1138.2 0.2631 1.5480 1.8111 180.0 l 182.0 7.850 0.016522 48.172 18.189 150 01 989.0 1139.0 0.2662 1.5413 1.8075 182.0 184.5 8.203 0 016534 46.232 46.249 152.01 987.8 1139.8 0.2694 1.5346 1.8040 1M.0 IIE.I 8.568 0.016547 44.383 . 44.400 154.02 986.5 1140.5 0.2725 1.5279 1.8004 186.0 f 188 0 8.947 0.016559 42.621 42.638 156.03 9853 11413 0.2756 1.5213 1.7969' 188.0 190.8 9.340 0.016572 40.941 40.957 158.04 984.1 1142.1 0.2787 15148 1.7934 190.0 192.0 9.747 0.016585 39337 39354 160.05 982.8 1142.9 0.2818 1.5082-1.7900 192.5 194.5 10.168 0 016598 37.808 37.824 162.05 981.6 1143.7 0.2848 1.5017 1.7865 1940 19EI 10.605 0.016611 36 348 36364 164.06 980.4 1144.4 0.2879 1.4952 1.7831 1968 l 198 I 11.058 0.016624 34.954 34.970 166.08 979.1 1145.2 0.2910 1.4888 1.7798 198.0 200 0 11.526 0.016637 33.622 33.639 168.09 977.9 1146.0 0.2940 1.4824 1.7764 200.0 1 l 204 8 12.512 0016664 31.135 31.151 172.11 975.4 1147.5 03001 1.4697 1.7698 294.8 208 8 13.568 0 016691 28.862 28878 176.14 9 72.8 1149.0 03061 1.4571 1.7632 208.I 212 8 14 6 % 0.016719 26.782 26.799 180.17 9703 1150.5 03121 1.4447 17568 212.0 i a 216.I 15.901 0.016747 24.878 24.894 184.20 967.8 1152.0 03181 1.4323 1.7505 216.0 229.0 17.186 0.016775 23.131 23.148 188.23 965.2 1153.4 03241 1.4201 1.7442 220.I 1 I 224.5 18.556 0.016805 21.529 21.545 192.27 962.6 1154.9 03300 1.4081 1.7380 224.0 1 2288 20.015 0 016834 20.056 20.073 19631 960.0 1156.3 03359 13 % I 1.7320 2288 232 8 21.567 0 016864 18.701 18.718 20035 957.4 1157.8 03417 13842 1.7260 232.8 236.8 23.216 0.016895 17.454 17.471 2 G3 954.8 1159.2 03476 13725 1.7201 236 O l l 248 8 24.% 8 0.016926 16304 16321 208.45 952.1 1160.6 03533 13609 1.7142 240.0 244.0 26.826 0.016958 15.243 15.260 212.50 949.5 1162.0 03591 13494 1.7085 244.8 l 2488 28.7 % 0.016990 14.264 14.281 216.56 946.8 1163.4 03649 13379 1.7028 248 0 t 252.0 30.883 0.017022 13 358 13375 220.62 944.1 1164.7 0.3706 13266 1.6972 252.8 256.8 33 091 0.017055 12.520 12.538 224.69 941.4 1166.1 03763 1.3154 1.6917 256.5 4 258 8 35.427 0.017089 11.745 11.762 228.76 938.6 1167.4 03819 13043 1.6862 260.8 1 264 9 37.894 0.017123 11.025 '11.042 232.83 935.9 1168.7 03876 1.2933 1.6808 264.0 258.8 40.500 0.017157 10.358 10 375 236.91 933.1 1170 0 03932 1.2823 1.6755 268O l 272.8 43.249 0 017193 9.738 9.755 240 99 930.3 11713 0.3987 1.2715 1.6702 272.0 i 276.8 46.147 0.017228 9.162 9.180 245.08 927.5 1172.5 0.4043 1.2607 1.6650 276.0 l 288 8 49.200 0.017264. 8.627 8 644 249.17 924.6 1173.8 0.4098 1.2501 1.6599 280.I 1 284 8 52.414 0.01730 8.1280 8.1453 253.3 921.7 1175.0 0.4154 1.2395 1.6548 284.8 288 I 55 795 0.01734 7.6634 7.6807 257.4 918.8 1176.2 0.4208 1.2290 1.6498 288I 1 I 297 8 59 350 0.01738 7.2301 7.2475 261.5 915.9 1177.4 0.4263 1.2186 I.6449 2978 l 296 0 63.084 0 01741 6.8259 6.8433 265.6 913.0 1178.6 0.4317 1.2082 1.6400 296.0 l

i i l 2 i i Abs Press. Specific Volume Enthalpy Entropy Sat. Temp Temp Lb per Sat. Sat. Sat. Sat. Sat. l Fahr SqIn. Liquid Evap Vapor Liquid Evap Vapor liquid Evap Vapor Fahr a t p vi vig vg hr h ig h sg sig sg t g 300.0 67.005 0.01745 6.4483 6.4658 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300.0 i 304.0 71.119 0.01749 6 0955 6.1130 2 73.8 907.0 1180.9 0.4426 1.1877 1.6303 304 0 300 I 75.433 0.01753 5.7655 5 7830 278.0 9040 1182.0 0.4479 1.1776 1.6256 30B O 1 312.0 79 953 0 01757 5.4566 5.4742 282.1 901.0 1183.1 0.4533 1.1676 1.6209 312.0 i 316.8 84.688 0.01761 5.1673 5.1849 286.3 897.9 1184.1 0.4586 1.1576 1.616: 316.8 320 0 89 643 0.01766 4.8961 4.9138 290.4 894.8 1185.2 0.4640 1.1477 1.6116 320.0 324.8 94 826 0.01770 4.6418 4.6595 294 6 891.6 1186.2 0.4692 1.1378 1.6071 324.0 328.0 100 245 0.01774 4.4030 4.4208 2987 888.5 1187.2 04745 1.1280 1.6025 328.0 i i 332.8 105.907 0.01779 4.1788 4.1966 302.9 8853 1188.2 0.4798 1.1183 1.5981 332.0 l 336.0 111.820 0.01783 3.9681 3.9859 307.1 882.1 1189.1 0.4850 1.1086.l.5936 336.0 } 348 0 117.992 0.01787 3.7699 3.7878 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340.0 j 344I 124.430 0.01792 3.5834 3.6013 315.5 875.5 1191.0 0.4954 1.0894 1.5849 344.0 i 348.0 131.142 0.01797 3.4078 3.4258 319.7 8 72.2 1191.1 0.5006 1.0799 1.5806 348.0 352.5 138 138 0.01801 3.2423 3.2603 323.9 868.9 1192.7 0 5058 1.0705 1.5763 352.0 356 8 145 424 0.01806 3.0863 3.1044 328.1 865.5 1193.6 05110 1.0611 1.5721 356.8 350.0 153 010 0.01811 2.9392 2.9573 3323 862.1 1194.4 0.5161 1.0517 1.5678 300.0 a 364.8 160.903 0.01816 2.8002 2.8184 336.5 858.6 1195.2 0.5212 1.0424 1.5637 364.0 368.5 169.113 0 01821 2.6691 2.6873 34Cs 8 855.1 1195 9 0.5263 II332 1.5595 368 0 372.8 177.648 0.01826. 2.5451 2.5633 345 0 851.6 1196.7 0 5314 1.0240 1.5554 372.8 376 I 186.517 0.01831 2.4279 2.4462 349.3 848.1 1197.4 0.5365 1.0148 1.5513 376.0 300.0 195.729 0.01836 23170 2.3353 353 6 844.5 1198.0 0.5416 1.0057 1.5473 300.0 304.8 205 294 0.01842 2.2120 2.2304 357.9 840 8 1198.7 0.5466 0.9966 1.5432 384.0 j 388.0 215.220 0 01847 2.1126 2.1311 362.2 837.2 1199.3 03516 0.9876 1.5392 388.8 i-392.8 225.516 0.01853 2.018A 2.0369 366.5 833.4 1199.9 0.5567 0.9786 1.5352 392.8 j 396.8 236.193 0.01858 1.9291 1.9477 370 8 829.7 1200.4 0.5617 0.9696 1.5313 396.0 400.0 247.259 0.01864 1.8444 1.8630 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400.0 404.8 258.725 0.01870 1.7640 1.7827 379.4 822.0 1201.5 0.5717 0.9518 1.5234 484.8 488I 270 600 0 0l875 1.6877 1.7064 383.8 818.2 1201.9 0.5766 0 9429 1.5195 400.0 4128 282.894 0.01881 1.6152 1.6340 388.1 814.2 1202.4 0.5816 0.9341 1.5157 412.0 l 415.8 295 617 0 0i887 1.5463 1.5651 392.5 810.2 1202.8 0.5866 0.9253 1.5118 416.0 l 420.0 308.780 0.01894 1.4808 1.4997 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420.0 424 8 322 391 0 01900 1.4184 1.4374 . 4013 802.2 1203.5 0.5964 0 9077 1.5042 424.8 428 8 336 463 0 01906 1.3591 1.3782 405 7 798.0 1203.7 06014 0 8990 1.5004 428.8 i 4328 351.00 0 01913 1302 % 132179 410.1 793.9 1204.0 0 6063 0 8903 1.4966 432.0 i 43E I 366 03 0.01919 1.24887 1.26806 414 6 789.7 1204.2 0.6112 0.8816 1.4928 435.5 1 J 440 8 381.54 0 01926 1.19761 1.21687 419.0 785.4 1204.4 0.6161 0 8729 1.4890 448.8 48 397.56 0 01933 1.14874 1.16806 3.5 781.1 1204.6 0 6210 0 8643 1.4853 fMC 414 09 0 01940 1.10212 1.12152 fric 776.7 1204.7 0 6259 0 8557 1.4,815 , N f. i

i i l ~ ) 1 i [ I Abs Press. Specific Volume Enthalpy Entropy l Temp Lb per Sat. Sat. Sat. Sat. Sat. Sat. Temp i Fahr SqIn. Liquid Evap Vapor Liquid Evap Vapor Liquid Evap Vapor Fahr j t p vi vig vg h t h ig h St 5ft 5: I e 468.I 466.87 0.01961 0.97463 0.99424 441.5 763.2 1204.8 0.6405 0.8299 1.4704 464.8 i 464.8 485.56 0.01 % 9 0.93588 0.95557 446.1 758.6 1204.7 0.6454 0.8213 1.4667 464.5 468.I 504.83 0.01976 0.89885 0.91862 450.7 754.0 1204.6 0.6502 0.8127 1.4629 488.0 4 412.0 524.67 0.01984 0 86345 0.88329 455.2 7493 1204.5 0.6551 0.8042 1.4592 472.0 j 475.0 545.11 0.01992 0.82958 0.84950 459.9 744.5 12043 0.6599 0.7956 1.4555 4FE.8 400.0 566.15 0.02000 0.79716 0.81717 464.5 739.6 1204.1 0.6648 0.7871 1.4518 480.0 484.0 587.81 0.02009 0.76613 038622 469.1 734.7 1203.8 0.66 % 03785 1.4481 484.0 1 } 488.I 610.10 0.02017 0.73641 0.75658 473.8 7293 1203.5 0.6745 03700 1.4444 480.0 1 492.8 633.03 0.02026 0.70794 0.72820 478.5 724.6 1203.1 0.6793 01614 1.4407 452.0 l 1, 496 I 656.61 0.02034 0.68065 010100 483.2 719.5 1202.7 0.6842 03528 1.4370 496.8 l 3 1 500.0 680.86 0.02043 0.65448 0.67492 487.9 7143 1202.2 0.6890 03443 1.4333 508.0 I 504.5 705.78 0.02053 0.62938 0.64991 4923 709.0 12013 0.6939 03357 1.42 % 504.0 I 508 I 731.40 0.02062 0.60530 0.62592 497.5 7033 1201.1 0.6987 0.7271 1.4258 500.8 y 512.0 757.72 0 02072 0.58218 0.60289 5023 698.2 1200.5 0.7036 0.7185 1.4221 512.0 515.0 784.76 0.02081 0.55997 0.58079 507.1 692.7 1199.8 03035 07099 1.4183 515.0 4 528.0 812.53 0.02091 0.53864 0.55956 512.0 687.0 1199.0 03133 01013 1.4146 520.0 524.8 841.04 '002102 0.51814 0.53916 516.9 6813 1198.2 03182 0.6926 1.4108 524.0 528 I 870 31 0.02112 0 49843 051955 521.8 675.5 11973 03231 0.6839 1.4070 528.8 i. 332.8 900.34 0.02123 0.47947 ' O.50070 526.8 669.6 1196.4 0.7280 0.6752 1.4032 532.8 535.8 931.17 0.02134 0.46123 0.48257 5313 663.6 1195.4 0.7329 0.6665 1.3993 536.0 1 540.0 962.79 0.02146 0.44367 0.46513 536.8 657.5 1194.3 0.7378 0.6577 13954 540.0 544.0 995.22 0.02157 0.42677 0.44834 541.8 6513 1193.1 0.7427 0.6489 1.3915 544.0 ^ 548.0 1028.49 0.02169 0.41048 0.43217 546.9 645.0 1191.9 03476 0.6400 1.3876 548.0 552.5 1062.59 0 02182 039479 0.41660 552.0 638.5 1190.6 03525 0.6311 1.3831 552 0 556.0 1097.55 0.02194 0.37966 0.40160 557.2 632.0 1189.2 0.7575 0.6222 1.3797 556.0 l l 580.0 1133.38 0.02207 036507 038714 562.4 6253 1187.7 03625 0.6132 1.J757 550.8 564 8 1170.10 0.02221 035099 037320 567.6 618.5 1186.1 0.7674 0.6041 1.3716 564 I l 568.8 1207.72 0 02235 033741 035975 572.9 611.5 1184.5 03725 0.5950 13675 588.8 i 572.5 1246.26 0.02249 032429 034678 5783 604.5 11823 03775 0.5859 1.3634 512.0 l 576.0 1285.74 0.02264 031162 0 33426 5833 597.2 1180.9 0.7825 0.5766 1.3592 575.8 l 580.0 1326.17 0.02279 0.29937 032216 589.1 589.9 '1179.0 03876' O.5673 13550 580.0 5840 1367.7 0.02295 0.28753 031048 594.6 582.4 1176.9 03927 0 5580 13507 584I i 588.0 1410 0 0.02311 0 27608 0 29919 600 1 5743 1174.8 03978 0 5485 1.3464 588.I l 592.0 1453 3 0.02328 0.26499 0.28827 6053 566.8 1172.6 0.8030 0 5390 1.3420 592.0 596I 1497.8 0.02345 0.25425 0.27770 611.4 558.8 1170.2 0.8082 0.5293 13375 595.0

Abs Press. Specific Volume Enthalpy Entropy Temp Lb per Sat. Sat. Sat. . Sat. Sat. Sat. Temp Fahr SqIn. Liquid Evap Vapor Liquid Evap Vapor Liquid. Evap Vapor Fahr hg h sg sig s i I p vg vie vg he i g g EOS 8 1543.2 0.02364 0.24384 0.26747 617.1 550 6 1167.7 0.8134 0.5196 1.3330 500.8 I 584 8 1589.7 0.02382 0.23374 0.25757 622.9 542.2 1165.1 0.8187 0.5097 1.3284 584.0 588 I 1637.3 0.02402 0.22394 0.24796 628.8 533.6 1162.4 0.8240 0.4997 1.3238 588.8 E12.8 1686.1 0.02422 0.21442 0.23865 634 8 524.7 1159.5 0.8294 0.4896 1.3190 512.0 516.5 1735.9 0.02444 0.20516 0.22960 640.8 515.6 1156.4 0.8348 0.4794 1.3141 E16.5 E20.8 1786.9 0.02466 0.19615 0.22081 646.9 506.3 1153.2 0.8403 0.4689 1.3092 E20.I $24.8 1839 0 0 02489 0.18737 0.21226 653.1 406.6 1149.8 0.8458 0.4583 1.3041 624.0 528 O 1892.4 0 02514 0.17880 0 20394 659.5 486.7 1146.1 0.8514 0.4474 1.2988 528.8 E32 O 1947.0 0.02539 0.17044 0.19583 665.9 476.4 1142.2 0.8571 0.4364 1.2934 537.8 E36.8 2002.8 0.02566 0.16226 0.18792 672.4 465.7 1138.1 0.8628 0.4251 1.2879 536.0 548 8 2059.9 0.02595 0.15427 0.18021 679.1 454.6 1133.7 0.8686 0.4134 1.2821 640.0 544 8 2118.3 0.02625 0.14644 0.17269 685.9 443.1 1129.0 0.8746 0.4015 1.2761 644.8 l E4B O 2178.1 0.C2657 0.13876 0.16534 692.9 431.1 1124.0 0.8806 0.3893 1.2699 648.0 552.8 2239.2 0.02691 0.13124 0.15816 700.0 418.7 1118.1 0.8868 0.3767 1.2634 552 1 j y 556 O 2301.7 0.02728 0.12387 0.15115 707.4 405.7 1113.1 0.8931 0.3637 1.2567 555.0 .co 560.0 2365.7 0.02768 0.11663 0.14431 714.9 392.1 1107.0 0.8995 03502 1.2498 888.8 $64.0 2431.1 0.02811 0.10947 0.13757 722.9 377.7 1100 6 0.9064 0.3361 1.2425 664.0 558 8 2498.1 0.02858 0.10229 0.13087 731.5 362.1 1093.5 0.S137 0.3210 1.2347 668.0 572.0 2566.6 0.02911 0.09514 0.12424 740.2 345.7 1085.9 0.9212 0.3054 1.2266 572.5 575.0 2636.8 0.02970 0.08799 0.11769 749.2 328.5 1077.6 0.9287 0.2892 1.2179 575.0 $88.9 2708.6 0.03037 0.08080 0.11117 758.5 310.1 1068.5 0.9365 0.2720 1.2086 680.8 4 584.8 2782.1 0.03114 0.07349 0.10463 768.2 290.2 1058.4 0.9447 0.2537 1.1984 584.0 778.8 268.2 1047.0 0.9535 0.2337 1.1872 588.8 588.8 2857.4 0.03204 0.06595 0.09799 ES2.8 2934.5 0.03313 0.05797 0.09110 790.5 243.1 1033.6 0.% 34 0.2110 1.1744 ES2.0 i E96.8 3013.4 0.03455 0.04916 0.08371 804.4 212.8 1017.2 0.9749 0.1841 1.1591 E96.0 l 700.0 3094.3 0.03662 0.03857 0.07519 822.4 172.7 995.2 0.9901 0.1490 1.1390 700.8 702 0 3135.5 0.03824 0.03173 0.06997 835.0 144.7 979.7 1.0006 0.1246 1.1252 702.8 7040 3177.2 0.04108 0.02192 0.06300 854.2 102.0 956.2 1.0169 0.0876 1.1046 704.0 705 0 31983 0.04427 0.01304 0.05730 873.0 61.4 934.4 1.0329 0.0527 1.0856 705.0 705,47* 3208.2 0.05078 400000 0.05078 906.0 0.0 906.0 1.0612 0.0000 1.0612 705.47* b Critical temperature [ f

i i i 1 I Table 2: Saturated Steam: Pressure Table i I Specific Volume Enthalpy Entropy i Abs Press. Temp Sat. Sat. Sat. Sat. Sat. Sat. Abs Press. Lb/Sq In. Fahr Liquid Evap Vapor Liquid Evap Vapor Liquid Evap Vapor Lb/Sq in. p t vg v gg v hg hgg h sg s gg s g g g p i 8.88865 32.018 0.016022 3302.4 3302.4 0.0003 1075.5 1075.5 0 0000 2.1872 2.1872 0.08055 3 25 59.323 0 016032 1235.5 1235.5 27.382 1060.1 1987.4 0 0542 2.0425 2.0967 8.25 8 50 79.586 0.016071 641.5

41.5 47.623 1048.6 1096.3 0.0925 1.9446 2.0370 0.50 i

1.5 101.74 0 016136 333.59 J33 60 69.73 1036.1 1105.8 0.1326 1.8455 1.9781 1.8 5.0 162.24 0.016407 73.5G 73.532 130.20 1000.9 1131.1 0.2349 1.6094 1.8443 5.0 18.5 193.21 0 016592 35.404 38.420 161.26 982.1 1143.3 0.2836 1.5043 1.7879 18.0 14$96 212.00 0.016719 25.782 26.799 180.17 970.3 1150.5 0.3121 1.4447 1.7568 14.596 l 15.8 213.03 0 015726 26.274 26.290 181.21 969.7 1150.9 0.3137 1.4415 1.7552 15.0 t ) 20.0 227.96 0.016834 20.070 20.087 196.27 960.1 1156.3 0.3358 1.3962 1.7320 20.0 1 30 0 250.34 0.017009 13.7266 13.7436 218.9 945.2 1164.1 0.3682 1.3313 1.6995 30.0 l 48.0 267.25 0.017151 10.4794 10.4 % 5 236.1 933.6 1169.8 0.3921 1.2844 1.6765 40 0 J 50 0 281.02 0.017274 8.4%7 8.5140 250.2 923.9 1174.1 0.4112 1.2474 1.6586 50.0 58 I 292.71 0.017383 7.1562 7.1736 262.2 915.4 1177.6 0.4273 1.2167 1.6440 60 I 70 g 302.93 0.017482 6.1875 6.2050 272.7 907.8 1180.6 0.4411 1.1905 1.6316 70 I ] Y 88 0 312.04 0.017573 5.4536 5.4711 282.1 900.9 1183.1 0.4534 1.1675 1.6208 10.8 e 98.9 320.28 0.017659 4.8779 4.8953 290.7 894.6 1185.3 0.4643 1.1470 1.6113 90.8 100 0 327.82 0.017740 4.4133 4.4310 298.5 888.6 1187.2 0.4743 1.1284 1.6027 100.0 118.3 334.79 0 01782 4.0306 4.0484 305.8 883.1 1188.9 0.4834 1.1115 1.5950 110.0 128 I 341.27 0.01789 3.7097 3.7275 312.6 877.8 1190.4 0.4919 1.0960 1.5879 123 0 138 I 347.33 0.017 % 3.4364 3.4544 319.0 872.8 1191.7 0.4998 1.0815 1.5813 130.0 140 0 353.04 0.01803 3.2010 3.2190 325.0 868.0 1193.0 0.5071 1.0681 1.5752 140.0 150 g 358.43 0.01809 2.9958 3.0139 330.6 863.4 1194.1 0.5141 1.0554 1.5695 150 I 168 8 363 55 0.01815 2.8155 2.8336 .336.1 859.0 1195.1 0.5206 1.0435 1.5641 168.8 1 17ee 368.42 0 01821 2.6556 2.6738 341.2 854.8 11 %.0 0.5269 1.0322 1.5591 178 8 133.3 'l73.08 0 01827 2.5129 2.5312 346.2 850.7 11 %.9 0 5328 1.0215 1.5543 180 0 19s.s 377.53 0 01833 2.3847 2.4030 350.9 846.7 1197.6 0.5384 1.0113 1.5498 190.8 4 I 2tg a 381.80 0.01839 2.2689 2.2873 355.5 842.8 1198.3 0.5438 1.0016 1.5454 200.8 210.8 385.91 0 01844 2.16373 2.18217 359.9 839.1 1199.0 0.5490 0.9923 1.5413 210.8 ) 220 0 389.88 0 01850 2.06779 2.08629 364.2 835.4 1199 6 0.5540 0.9834 1.5374 220 0 4 23e e 393.70 0.01855 1.97991 1.99846 368.3 831.8 1200.1 0.5588 0.9748 1.5336 230 I I 248 3 397.39 0.01860 1.89909 1.91769 372.3 828.4 1200.6 0.5634 0.9665 1.5299 248 I i 253 8 400.97 0.01865 182452 1.84317 376.1 825.0 1201.1 0.5679 0.9585 1.5264 250 I i 268 0 404 44 0 01870 1.75548 1.77418 379.9 821.6 1201.5 0 5722 0 9508. 1.5230. 268 0 l 278 8 407.80 0 01875 169137 1.71013 383.6 818.3 1201.9 05764 0.9433 1.5197 278 0 2000 411 07 0 01880 1.63169 1.65049 387.1 815.1 1202.3 0.5805 0.9361 1.5166 200 0 2900 414.25 0 01885 1.57597 1.59482 390.6 812.0 1202.6 0.5844 0.9291 1.5135 290.0 300 3 417.35 001889 1.52384 1.54274 394.0 808.9 1202.9 0.5882 0.9223 1.5105 308 I 350 8 431 73 0 01912 1.30642 1.32554 409 8 794.2 1204.0 0 6059 0.8909 1.4968 350 0 400 0 444 60 0 01934 1.14162 1.16095 424.2 780.4 1204.6 0 6217 0 8630 1.4847 408 8

] Specific Volume Enthalpy Entropy Abs Press. Temp Sat. Sat. Sat. Sat. Sat. Sat. Abs Press. 1 tblSq In. Fahr Liquid Evap Vapor Liquid Evap Vapor Liquid Evap Vapor. Lb/Sq In. f8 '8 hg hgg h sg s g, s p p t vg v g g 450 8 456 28 0 01954 1.01224 1.03179 437.3 767.5 1204.8 0.6360 0.8378 1.4738 450.0 l 580 8 467.01 0 01975 0.90787 0.92762 449.5 755.1 1204.7 0.6490 0.8148 1.4639 500.0 1 558 I 476.94 001994 0 82183 0.84177 460.9 7433 12043 0.6611 0.7936 1.4547 550 I EOS I 486 20 0 02013 0.74962 0.76975 471.7 732.0 1203.7 0.6723 0.7738 1.4461 600.0 4 658 8 494 89 0 02032 0 68811 0.70843 481.9 720.9 1202.8 0.6828 0.7552 1.4381 650.0 4 700 8 503 08 0 02050 0.63505 0.65556 491.6 710.2 1201.8 0.6928 0.7377 1.4304 700.8 1 758 I 510 84 0 02069 0.58880 0 60949 500.9 699.8 1200.7 0.7022 0.7210 1.4232 750 I i 800 8 518 21 0.02087 054809 0.568 % 509 8 689.6 1199.4 0.7111 0 7051 1.4163 808 I [ 158 8 525 24 0 02105 0 51197 0.53302 518.4 679.5 1198.0 0.7197 0 6899 1.4096 850 8 900 3 531.95 0 02123 0.47 % 8 0.50091 526.7 669 7 11 %.4 0.7279 0.6753 1.4032 900 0 950 0 53839 0 02141 0 45064 0.47205 534.7 660.0 1194.7 0.7358 0.6612 13970 950 8 1 1000 8 544.58 0 02159 0.42436 0.445 % 542.6 630.4 1192.9 0.7434 0.6476 13910 1000 I i 1958 8 550 53 0 02177 040047 0.42224 550.1 640.9 1191.0 0.7507 0.6344 13851 1850 0 { 11000 556.28 0 02195 0 37863 0 40058 557.5 631.5 1189.1 0.7578 0.6216. 13794 1100.I 1150 0 561.82 0 02214 035859 038073 564.8 622.2 1187.0 0.7647 0.6091 13738 11508 ~ 12000 567.19 0.02232 034013 036245 571.9 613.0 1184.8 0.7714 0.5969 1.3683 1200.5 j i 1258 8 57238 0.02250 032306 034556 578.8 603.8 1182.6 0.7780 0.5850 13630 1258.8 1300 0 577.42 0 02269 030722 032991 585.6 594.6 1180.2 0.7843 0.5733 1 3577 1300 8 13500 58232 0 02288 0 29250 0 31537 592.3 585.4 1177.8 0.7906 0.5620 13525 1350e i 14000 587.07 0 02307 0 27871 030178 598.8 576.5 11753 0.7966 0.5507 13474 1400.8 j 14500 591.70 0.02327 0.26584 0.28911 6053 567.4 1172.8 0 8026 0.5397 1.3423 14508 t f. 15000 596 20 0 02346 0 25372 0 27719 611.7 558.4 1170.1 0.8085 0.5288 13373 1500 O ) o 15500 600 59 0 02366 0 24235 0 26601 618 0 549.4 1167.4 0.8142 0 5182 13324 15500 15000 604 87 0 02387 0.23159 0 25545 624.2 540.3 1164.5 0 8199 0.5076 13274 16005 4 l 16500 609 05 0 02407 0 22143 0 24551 630.4 5313 1161.6 0 8254 04971 13225 1550 0 17000 613.13 0 02428 0.21178 0.23607 636.5 522.2 1158 6 0.8309 0.4867 13176 17000 .l 17508 617.12 0.02450 0.20263 0.22713 642.5 513.1 1155.6 0.8363 0.4765 13128 1750I 1880 0 62102 0 02472 0.19390 0.21861 648.5 503 8 11523 0 8417 0.4662 13079 1800 0 18500 624 83 0 02495 0 18558 0.21052 654.5 494.6 1149.0 0 8470 0.4561 13030 1850 8 4 19800 628 56 0 02517 0.17761 0.20278 660.4 485.2 1145 6 0.8522 0 4459 1.2981 1900 0 a 1950I 632 22 0 02541 0.16999 0.19540 liS63 475.8 1142.0 0.8574 0.4358

• 1.2931 19500 20000 635.80 0 02565 0.16266 0.18831 672.1 466.2 11383 0.8625 0 4256 1.2881 2000 I i

2100.0 642.76 0 02615 0.14885 0.17501 683.8 446.7 1430.5 0 8727 0 4053 1.2780 2100 1 22008 64945 0 02669 0.13603 0.16272 695.5 426.7 1122.2 0.8828 03848 1.2676 22003 23000 655 89 0 02727 0.12406 0.15133 707.2 4060 1113.2 0.8929 0 3640 1.2569 23008 4 l 24000 662.11 0.02790 0.!!287 0.14076 719.0 384.8 1103.7 0.9031 03430 1.2460 24000 l 2500 0 668.11 0.02859 0.10209 0.13068 731.7 361.6 1093 3 0.9139 03206 1.2345 2500O l 26000 673 91 0.02938 0 09172 0.12110 744.5 337.6 1082.0 0.9247 0 2977 1.2225 2500 0 l 2700 0 679 53 0 03029 0 08165 0.11194 -7573 3123 1069.7 0 9356 0.2741 1.2097 27000 4 2000 0 684 96 0 03134 0 07171 0 10305 770 7 285.1 1055.8 0.9468 0.2491 1.1958 2800 0 2900 0 69022 0 03262 0.06158 0 09420 785.1 254.7 1039.8 0.9588 0.2215 1.1803 2900 0 3000 0 695 33 0 03428 0 05073 0 08500 801.8 218 4 1020.3 0.9728 0.1891 1.1619 3000 0 3100 0 700 28 0 03681 0 03771 0 07452 824.0 1693 9933 0.9914 0.1460 1.1373 31000 32000 705 08 0 04472 0 01191 0 05663 875.5 56 1 931.6 1.0351 0 0482 1.0832 3200 0 08.2* 705.47 0 05078 0 00000 0.05078 00 906.0 1.0612 0.0000 1.0612 8.2*

Table 3. Superheated Steam Aes heS6 LW541a Set Sal Te=0cature-Degrees Talvenheit ($at. temet Walev 5:aam 200 250 300 350 400 458 500 Set 700 000 900 1000 lidt litt g Sh MM 148 M 198 M N8 M 298 M M826 390 M 490 M HI M 890 26 790 M 800 3 te8 M less F6 e 9 01614 333 6 M25 422 4 452 3 442 1 Sill 541 7 571 5 431 1 698 7 Me) 809 0 est e 9M e 980 6 1101 748 6 09 73 115 8 1150 2 1872 9 1895 7 1210 7 BNie 12651 1780 6 13M I 1384 1 1833 7 las38 ISM 9 IS068 16M 7 s 4 1336 I.9781 2 500 2 Seal 2.1152 2 leal 2 1722 2 1985 2 2237 2 2700 2 3144 2 Mll I19M 242M 2 e680 2eM9 Sh 37 M 87 M IH 76 18F 76 737 M M7 76 337 4 43776 537 4 437 76 FIF 76 837 76 937 M len 76 I 0 41641 7353 70 14 to 73 90 24 96 ?S 107 N B00 H 114 71 IM 15 IN 00 IS408 161 94 in M 105 F8 197 70 e 1862 241 h IN 20 1131 8 1140 6 1871 7 lite t 1780 0 IN13 12W F 1708 7 13M 9 8384 3 1433 6 14037 15347 1546 7 1639 6 3 0 2349 1 0443 8.0186 8 90be 1 9369 8 90M i 9943 2 0200 2 Sete 20832 2IM9 2IH6 221H 22Sil 2JH6 2 3894 Sh 6 79 M 79 106 79 1 % 79 706 79 256 79 306 79 del F9 Set 79 006 79 706 79 806 79 tes 79 1006 F9 gg e M6M M 42 M ed 41 93 44 M 4H2 Sl o) 54 04 57 p 6303 M OS HM 88 94 86 98 W 47 M 88 1193 21) 6 141 M 1143 3 1146 6 8870 7 1893 7 1217 1 17806 1268 1 17878 11M S IM40 14334 14815 1534 6 1586 6 1639 5 s 42036 41079 830f0 la.N 8 593 1 8082 8 9473 1 9439 4 9697 2 0166 2 0603 2 1018 flMe 2 8757 2 2108 2N30 Sh Net N 00 130 00 180 08 2M 00 200 et 300 00 400 00 908 80 tes et 700 00 seM Me to le GM e 0847 M 799 20 of 30 52 32le M 67 NN 30 H a286 46 93 SI et SS M M 13 U 19 67 M (212 He b IN 87 liSe $ llea 0 1897 6 1714 3 17M 9 IM36 IM74 1335 7 8303 8 le p 7 leale ISM S llet S 8619 4 s 3Q8 1 7568 1 7833 3 31g IMg 1 87s3 IM10 19MS ltFM Itin 2 0$85 2 8000 213H 2 1676 2 200% $h M97 0R 97 1397 80697 IM 97 79697 306 97 40697 $0697 606 97 FM 97 80697 90697 39 9 01673 M 790 27 8H 29 899 38 9j9 H 943 35977 37 9 S 419m 45978 49 964 S3 944 57976 61 905 65887 e 1213 03) a 181 28 1150 9 1168 7 BlW S 8216 7 12M 9 IM36 1287 3 1335 2 1383 8 1433 7 1483 4 1534 5 1586 5 1639 4 e 8 0 3137 IJS$2 1 7899 181M 8 0437 1 9720 1 0008 19N2 1 9717 2 08 % 20$63 2 0946 2 1309 2163 28M7 Sh 72 04 77 04 ltf ee 17704 277 04 272 04 377 08 4H04 17704 SF70s 772 04 8720e 9?? 04 N e 0 01643 20 007 70 708 77 3 % 23900 75 478 M 946 20 4$7 31 846 M a65 H ate 40447 43en 46470 49 40S 027 Mi h 496 H 1156 3 18678 litl e 1715 4 IH97 IM10 1206 9 IH49 13835 1432 9 1483 2 1534 3 15a6 3 1639 3 5 433SS 8 7320 1 7475 17ml 1 8488 18M7 1 9066 1 9978 1 9397 1 9836 2 0244 20US 2 0991 2 3336 faut 3h 9 93 $9 93 IM 93 IS9 93 70993 PM 93 359 93 45993 SMll 65993 759 93 059 93 95993 pg e 0 01691 16 101 16 % 8 17 R79 19 fl16 70 in; 7i %n 7; F40 M 193 77 %%7 79 9%4 17 tet M Pa0 H 130 39 9:s gag gil b 71118 5 7 Iltn 6 1l6% 6 al'in P 17:44 8714 % IMPS 1746 4 14:46 lie s s 14177 14414 8%l47 1%er. 7 14h p t 0 3534 I 7148 i H17 I 7se7 i Few i eles I nalg i e677 1 9149 e noe i9n7 7 e vis 7 0/44 7 leire 7 lest 3" M 66 94 % M 66 99 # 789 66 M9 H 4M 66 Satu 64466 749 W 089 66 989 % 30 e 6 01701 13 744 84 010 Ils 9 6 092 7 914 18 979 70 945 77958 74 9%2 M 9st 70 983 309u M 937 010 M7 h lis t) llW 1 1109 0 1213 6 H18 Mit 1706 0 ID47 IN30 14H S 1487 8 1514 0 IS06 t 16M O S SM82 1699S 3 7334 I M47 1937 .ello 10867 1 0946 8 9306 I 9795 203 F9 2 0643 7GNS 21247 33 Sh 40 FI 90 FI 40 71 190 78 P40 fl M0 FI 440 78 $40 71 640 78 740 71 set 71 940 71 1 0 59 291 e 3 01708 Il 996 7 654 13 % 7 4 453 IS He il 707 IF M9 19447 ft 3F9 H 092 24 003 M Sl? 10 H0 h 2N 03 l1671 807 8 1712 7 2HB 1761 3 120$ $ 1333 9 IM28 14H 3 1442 7 ISH 9 1506 0 1638 9 8 SNet 168H

7157 1 7468 17MI 1 8035 1 8294 18H4 1 9714 1 9624 2 309 20H2 2 0717 7 1066 Sh 37 75 et FS 132 PS 107 75 237 FS 337 FS 487 FS $32 PS 637 FS fu PS 837 75 937 75 9 01713 19 497 10M 18 8M 12 674 13390 14 165 15685

F itt 18 699 N Its 71 697 1319e 74689 e

OU 2Sp h 2M ie ll69 8 IM 6 121t 7 12M 4 1260 8 1705 0 13336 382 5 84HI 1482 5 ISH 7 8505 8 16188 s S N21 46765 0087 1 7312 I MOS 1 7003 18143 18W4 19065 1984 1 9000 20H4 20M9 2 0099 48 Sh 25 % FS % lli$6 175 % Fil % 3M M 425 % brS % 6M % FM 56 875 % 9M $6 ON est

• S elFil 9 399 9 H7 le 497 il put II 092 82 5H 13 9H IS 2F6 le lie 17 950 19 702 M 613 21 913 h 243 49 1172 I lits 4 8210 4 1235 7 IMO2 1288 6 IH33 1307 3 5438 9 1482 3 1533 6 154S 7 I638 7 s S etti I G678 8 00e9 33873 IJ473 11748 8 8010 8 8892 100M l.9MS 197N 2 0093 2 04M 2 07H 88 18 90 68 10 ll8M 140 90 218 98 318 98 al0 M Sitte ll090 718 90 018 98 918 90 908 th Sh, gegyg; 8 514 8 769 9 828 19 e67 196a4 18 306 If ut 13 748 14 9e7 16 1 % IP HO 10 %sg 19 7a6 h

2$0 78 117a 1 1138 8 1709 9 I?M 9 1759 6 lita l 1332 9 8382 0 1431 7 1482 2 ISH e 1505 4 1630 6 6 0 ell! l 6506 86He i Fest iFM9 6 7620 1 7090 1 0374 1 0816 i WIF i Mi3 iMN 2 0322 2 ES2 le Sh 17 93 62 93 112 93 162 93 267 93 312 93 412 93 Sit t) 617 93 712 93 01293 912 93 l 907 Oil e 9 017H i 945 0 S46 9IM 9 702 le M7 11 M1 12 485 13 503 14 6H ll FH lt BM 17 948 a h {M el lit? 9 1700 9 17M 2 12M i 1283 6 13H 6 1381 8 tell S 1402 0 1533 3 ISOS S 16M $ e u 41% 1 4008 8 0033 47H7 1 Mit I litt i 84M 1 8710 i till I 9507 8 907 2 til 2en 80 th 7 79 6779 107 ft iSF 29 M7 29 NF 79 40F 79 507 79 80779 70729 807 F9 90779 0 92 718 e t elFM 7 174 FMF Isil 8 354 S tel 9 800 19 4M la 4M 12 446 13 450 le aS2 llant 16 450 t {G2 Il llH 4 1181 6 1700 0 IFH $ 4758 $ 8783 7 13323 1381 5 4431 3 leal 0 ISH 2 1585 3 1638 e $ s 4273 1 4440 16492 168M I FIM 3 7417 1 7608 1 8164 4 0612 8mN 1 9410 19He 2 0120 20e50 Sh g g; gg t? 197 02 157 07 207 07 302 07 40202 187 82 00202 702 07 80207 90207 88 e 4 01783 6 633 4 475 7195 7M7 8106 0667 9 All le %7 al 404 12 et t 13 3M le MI 15183 0 97 983 h 267 63 1179 8 l100 3 17070 1737 7 17579 1782 7 4331 9 1301 3 18318 1441 6 ISH O 150% 7 16M 3 e 54M4 1&HS I 6300 8 673) 3 7000 i H24 iFM0 180H I SSH I 8035 l9H8 l 9605 2 0031 20MI Sh 4707 9707 14707 19707 M7 0F M787 497 07 M7 07 69797 79707 89707 N e 0 01748 4 POS 4 6As 7IH 7 $90 8 039 09H 9 793 leEM ll M7 17387 13 740 le M7 (302 931 h l72 74 18034 1206 0 llH 0 IMP 3 1282 2 IHl4 IMie 14M9 1481 3 ISH9 ISel l 16?8 7 0 W edil i 6346 i e640 1 6958 i H37 8 1504 1 7993 184M i 80W l W38 8 964J l 9989 20H9 SR 4739 9239 147 39 192 39 19? M 397 39 492 39 $92 39 697 M 797 31 097 79 Pg e 803 F33 S 014 6 704 6 645 7 074 7 e94 83M 913$ 99a5 le no 11SS) 12 3 % alISS IMy Oil b 277 % 1881 9 U0% 0 till ? 12 % 7 Ull 7 1111 3 1390 7 1830 F leal 3 1S37 7 154$ 0 8618 i s 0 4474 1 6260 16M4 16#8 lille 17424 1 7985 IBMI 18H4 1 9864 195M l!8H 2 0202 Sh

• SUOff htet. I h
• fnth3lpy. Big per Ib V = 5p0Cif aC V0lumt. CU li per lb

$ = tolF0py, Blu ptf R per Ib B -3

Table 3. Supe 7hested Steam-Continued ADS Prelt. WS4 la Set Set femeeralvre-Oprees femeaheil (144 temet 90 alee Steam 330 400 450 See 550 000 100 000 000 1000 1100 3200 1300 14:8 Sh )1 96 67 96 13796 197 M HFW M7M 30796 40796 $3796 60796 70796 IBF M 90796 3c87M OS e 0 01757 $471 38N 6 788 4W2 7 018 7 400 7 794 OMO 9 319 10 075 19 879 11 581 12 334 13 081 IISi 0 12 008 h 20F il llH I 120e 8 1238 % IM6L 1281 3 1306 2 13309 D00 5 14305 Ital l 1632 6 lies t 6630 0 1692 0 5746 4 4 64M4 46MB 4 M73 3 6790 1 7000 IFM9 i Met I 1882 8 8209 8 4702 8 9009 I 9454 8 9000 2 043! 2 0846 2 D 13 74 83 74 133 74 I83 F4 133 78 M3 74 363 74 483 74 SS) F4 083 74 703 F4 883 78 903Pe 1083!s 08 e SGIF62 5167 3 een itot 4 773 6 597 4 966 7 330 0 062 8 768 9 400 10 190 IO 908 31604 12 als 13314 016Mi h 306 52 Ilp ! 1203 4 t2M i 12% g 17tal 1305 8 1330 6 1300 2 1430 3 leal 0 1532 4 1588 7 1637 9 3691 9 lias e s 84000 141M I H06 8 6746 1 7900 1 7279 81882 17H2 1 8220 18W4 1 9028 1 9306 13733 2453 2NF9 2 0682 th 29 72 79 72 179 72 179 72 229 f t fit ?? 379 FF 479 77 579 F2 679 72 779 77 879 77 979F2 (0F9!! 90 v 9 01706 8 005 lite 1 905 5 069 6 273 6 572 6 917 F 600 4 777 8 960 96P1 19 700 19 958 11 675 32292 08020 h 200 H llM 3 820F 0 1778 9 IM49 1780 3 1305 4 1330 2 1300 0 1430 1 1480 8 1532 3 isas 4 1637 8 1691 0 174 s 04H3 lall) 1 6323 t he6 I He9 1 7212 1 7467 37MP ISIM 1 8570 8 8067 13323 I t0H 2 0000 23386 2 0619 th 29 87 PS 67 IM47 Int? 725 53 2Mlf 3M87 4M 47 SPS S7 67S 87 F7507 87S 87 97507 10?% s7 M e 3 01770 4 658 east 1 705 6 %%I S tet 4 771 6 448 7 186 7H8 0 477 9 883 9 7e7 10100 11017 51843 0 34 131 h [9e 70 llE 7 3300 9 1223 I (2%83 (279 8 830g 0 8379 9 1379 9 1879 9 3420 6 D32 l 1$84 5 16377 5691 7 8744 6 e sette 1 4000 lA253 i Stet I 6876 8 7149 8 7404 8 44S 1 0094 I 8500 8 8097 8 9767 8 9009 8 9980 2 02 % 2 0519 D 22 18 F7IS IPP18 172le 27710 2FF 18 372 88 472 18 SFP 10 67718 77218 SFF18 977 18 1072 18 000 e $48774 8 438 4 900 49M S M6 $ 508 5 90s $ 216 6 833 7443 0 050 86% 9 758 9 060 19 444 litf4 ON SF) b 200 $4 1187 7 (199 9 17H 4 IMlf $2F91 1308 6 13M 6 D79 % 1479 7 laa0 4 ISN S ISta s 16376 1691 6 1745 5 s 04M3 148f 7 84887 i Hl6 8 6014 4 7006 8 7344 8 Fle6 8 anM i MSI 188M 1 9205 I 9662 89NJ 2 Sitt 2 0$02 th 18 63 6663 l144) 968 63 21463 M863 36863 46863 Mll) 06463 M463 $$863 Mall 106663 108 e 8 03778 4HI 4 M9 4 690 $ 807 1 38% $ 6t f $ 91% 6 S04 70e6 Pan 8 741 0 016 9 389 9 968 lenn 4331 3 4 h 302 24 lien 0 litt 8 17M 6 IM31 1778 8 130s 7 13M P 1379 7 1479 4 1440 3 1531 8 Inte 7 1637 5 1691 S list a 8 04790 1 3908 168 2 teen sein 3 70JI I nOS lin30 B M01 18ms is705 S till 19eef 89ere 2014s 2 0844 19 71 Gul IM 71 IM PI 7lg 71 Mg 71 365 78 e6s 71 Ms71 66571 7es71 06571 966 71 806s ti fit e 9 0.707 east o let o ut a 777 gm8 g yd g ae7 6 7e% 6 7al 7 33e Fan Sail Gul 9 %87 lemi OM 791 h 30% 80 1108 9 liti f 17M e 17 9 % 1774 3 13018 19s9 13M 0 tem 7 leat t Isil l Itas i 1637 4 16H e 17 44 s 0asse Iwie Iatti i Ug6 1 6600 1 4975 IFH3 1 7476 1 7970 183s4 8 Sin I 9009 Itoes t9HF 2 8003 2 0397 D 81 92 li t! 111 9? 16197 211 92 Mi tt M192 461 92 Mi t? 06192 M192 868 97 Mit! 196197 Ill e 9 0l 79% 3 001 3 957 e MS 4 990 e tsi 5 119 S 392 Stu 6 46% 6 994 7 578 the 8 570 9 093 9 61% 03405 6 389 75 ligt e 1896 7 122S 4 12%t t 18779 1213 llM 6 1378 8 1479 0 1879 9 1531 6 llee t 14372 1691 4 IFall 8 4 4077 1.M13 iANI i Het i M44 8HN I 7841 4 742$ 81877 I8M4 1 0882 1 test ! 9396 8 9727 2 8064 2 8347 sh 8 73 58 73 158 73 Its F'3 208 73 250 73 358 73 4St 73 568 F3 MS F3 Pl8 F3 058 F3 Me 73 10$4 73 Ist e 9 01709 3 F775 3 7811 4 0F06 4 Mle 4 H41 4 9009 51637 $ 6813 6 1978 4 7006 7 2060 # 70M 8 2849 8 7130 t rise 0412h 6 312 58 1190 4 1895 6 1774 1 3251 2 1777 4 1302 9 1320 2 1378 4 1470 8 1479 8 Il314 19439 86371 1691 3 1744 7 8 84049 1 5879 13043 1 6206 I 6992 I NF2 41832 8 7376 1 7029 8 tre6 ISMS ISWI Itast i H00 1 9996 2 9330 Sh 267 5267 19767 15267 20f 67 25267 21247 4S767 M247 45267 71247 tillt 9526f 16767 130 p 0 01796 3 4544 3 4099 3 7ett 4 0179 4 M72 4 SISI e 7109 52304 5 7118 6 1814 4 4806 7 lidt 7 5781 8 Dell 8 53!) IMP 33 h 386 95 8198 7 1893 4 1222 9 37e99 1776 4 13071 1327 % 43H1 4420 4 14794 lt!t t l%43 6 l6M 9 l691 6 5144 4 s 6400s 13s83 83033 1 688 lastl Isnt l>$p 83203 1347 l aill lael tagli ism 9 Ist03 1 9:07 !alli 46 96 elm 146 96 196 96 286 96 M6 M delN 986 M 686 96 N6 M tes 96 98696 less 96 les e 9 01803 3 7390 3 e063 37143 39h76 41684 e 4119 eagee $7905 S H64 6 1709 Seen leset Pen 2 Ista6 1353 0 4 h ]I4 96 1193 0 12M8 8248 7 12FS 3 1301 3 13M S IH74 1479 0 84798 IS308 1483 4 66M t 1698 9 lisS 9 s m9073 13752 18NS I MOS 1 6806 1 9989 IJIN IJE2 100FI 1 8068 lagt0 1914 1 9908 3.90ft 2 0:29 4157 9117 14ll7 19957 Milt 38157 44157 541 57 68157 74157 04157 98157 leen SF 191 e 901N0 30199 3 7700 3e%$ 3 6799 3 0918 4 :112 eSMS 4 9871 5 3307 SFM8 6 1412 4 M82 6 9661 F Ell plt 4JI a 330 H lite i 1219 I INF4 127e 3 1300 5 11M i 1376 9 1477 4 le 78 7 ISM S IS831 16M S 4690 7 1745 F S 65848 litel I 9903 1 6313 1 6802 4457 8 Fall 8 7573 1 7997 ISM 3 iSMI I 9000 iMal I 9744 2 0062 sh 36 45 88 45 IM el 18645 2N el 136 45 4M 45 Swel 4M et FM et eM eg 9M el 10M a$ 100 e gesell 281M Stese 37788 3 44l3 3 6869 3 3800 4 7470 e pts t elH S 3981 S FF44 4tM2 6 %291 6 90 % g3 Hill 6 336 47 1195 1 1217 4 42e6 0 12F3 3 1299 4 13M e 13M 4 14H 2 1470 4 1530 3 8687 9 16M 3 1490 $ 17e5 6 s 4 5306 iSpl 13s06 8 6231 l6u2 86790 l>0M 1349e 17989 Iuit i467s Iter 7 89M9 8964 I toto gh 38 58 81 %8 131 $8 leile 231M 331 58 431 60 131 58 411 50 731 %8 03t 58 til g8 tell g6 lit e 0 05031 Pl?M 2 0162 3 0788 3 H06 34MS 36tM 3 N79 eMM 4 715S 5 0749 1 832% $ 7000 41440 l ett) l 4364 421 h golfe litt e 1215 6 12e4 7 1H22 1294 0 4324 7 137S 0 leM 8 8470 0 l%30 0 l%87 6 16M t 4498 4 17a%4 e sS200 llMI 13623 161$7 1 6847 1 6717 1 6004 1 7428 17He 10H6 1 9610 letH 19MI 1 9000 1 9983 D M 92 M 97 IM 97 lM 97 FM 97 3M 97 4M 97 176 97 eM 97 FM 93 OM 97 9M 97 igm 97 000 e 0 91877 25317 2 8474 2 0iOO 3 esu 3 7706 3e093 3 7678 4 1004 4 4300 e 7907 S e70s $ 46S 7 S eele GIMI 07300 6 3e619 1196 9 1713 8 1743 4 1271 I 1797 9 IH40 137% 3 l4M 3 14777 ISM P l%87 4 16M 9 64M f iT4% 3 5 $l320 lite) llM3 1 6070 86H6 lust B H00 17M2 1 7704 8 8176 I Stel I t004 192H 1 9685 196e9 Sh H47 F2 47 lit et 17747 27747 322 4 F 42287 $2747 622 47 72f 4F 8??47 97141 16?7 47 pte e 0StaH 2 8030 2eMi 2 6915 2 sFS4 3 H29 3 7744 3 Mel 3 0009 4 7140 4SMS 4 alF7 61764 iets9 5 01:a OH HI h Me te B197 6 4212 0 8247 0 8270 1 1797 1 1H33 1374 8 84M 9 14774 8%F94 l%42 l 141% 7 1698 0 IFa$l s OSM4 liete I M47 16006 16MF I Hel 164M 1 7299 I H22 1 8115 l este 88M4 1 9866 1 9404 8 9749 th 19 70 64 70 180 ?0 2 0,70 leses 337:3 3 69is 4 0000 4 30H e stil 4 9:45 $ 719 $ 5709 168 210 70 fl8 N 410 78 51870 688 30 718 N 0t0 70 918 N 8410 ?O 900 e 0 0:039 2 7073 23%*e tsaae 7 77e7 39 IMi tel b Mtli 1998 ) 17:0 1 1280 6 BM90 12% P llH 4 Infe 3 I4M g 64774 nP9 5 gg8t t 16M 4 6409 6 67ag s s SMM 16e64 llM3 BMM I U42 I Ml8 8 6773 1 7239 llM3 1 8057 194M 1 8776 1 9199 19427 1 9732 $h = superheat. f h = enthalpy. Stu pe7 lb 9 = Specstic welume, tu il per Ib 5 = entropy, Stu per F pe7 lb B -4

e 'S Table 3. Supe 7 heeled Sleem-Continued S' gel e,l le.Seralwe.0ccees lawcase.1 l is.08 Mel $~ .00 .M = MS. . MS MM .IM

i. iMO

.400 1500 h lett HM 114 00 IMM Plo tt han el4M ll4 M 684 09 fleM 014 00 91409191400 811e06 Ret e 0 01084 7 1077 77N4 24:08 3 s000 3 730s 2 9070 371H 3 SIN 3 0000 4 0007 e Mit 4 408 4 909 s ystl 3 544o 1806 911 h Netl IING 170007 12M 2 IM00 BMS 3 1378 9 1373 7 leM I B476 7 BWOS 1501 6 16M 2 8409 6 l7se t 6800 0 8 49800 IMl3 I Mit 19072 1 6:00 4 6850 1 6715 3 F407 1 7007 IONI 1 9378 1 9778 19864 ItN2 1964 I M70 h 1917 telt 110 82 Mtit #10 12 Helt 4017 590 17 61012 710 17 01017 980 12 3010 12 1110 17 fle e 80150 2 00s3 t itet 2 2999 24He 26199 2 7710 306st 33tes 36327 3 9175 4 1995 d e671 4 M26 1 9173 5 7913 000m a Non7 Iin 6 INE3 1237 0 8206 9 179s 5 1328 2 1373 2 14M F leM 3 1520 6 1981 4 ISM 0 NOS 4 IMe7 8000 6 6 SMet 13374 lasta 15N8 16&N leste lette 17820 litM 1 7988 4Allt lates 19003 ItNG 1 9675 1 919 Sh 6 30 WN B06 W IM N 306 m 30630 404 N 906 N 05 30 706 N NE 30 906 N 1906 N lies N 338 e 8 00059 1 9005 30!!! 2 1919 2 M03 2 9000 7 6461 2924 320ft 3 e??6 3 N06 4 0080 4 7787 a ull 4 7954 1 9606 1303 70 t 350 20 8200 1 120s 4 12M 3 1285 7 12536 1320 4 1372 7 lO42 1476 0 1520 2 Stel i IQ48 legt 3 1Me1 8000 S s SMet Blast lHOS 45747 IANI 16M4 lages 4J075 17ter 17007 14360 latte 18062 letM l.96 4 190H th ISI $241 197 6) 352 68 30768 307 61 402 61 182 40 00368 4261 052 68 903 61 8002 61 1107 61 See e 0 00000 1 9177 1 9280 200P0 2 7467 F Mll 2 5316 200P4 3 0064 3 3799 3 5631 3035 4 0476 eMM 4 5477 4 0892 0 97 305 h 372 77 1700 6 IMP 4 12M t 8764 6 1797 7 1319 7 1377 5 54210 147$ 4 16279 19N 9 86M 6 1600 0 IM83 10004 8 4304 13799 44330 S M07 19N6 BAftl 8 6562 1 7025 174U 1 7080 1 9219 10HO 8 000s 1 9723 ltWe ItH2 - Oh alN M01 149 03 19003 209 03 30903 499 03 900 03 009 03 70003 SM03 99903 1999 H III e 80859 1 9832 7N16 3 1500 3 rg80 faM2 r e872 2 9810 3 1999 34367 36037 3 9770 a lr09 s ein 4 6586 leN971 h 3M le l201 l 4233 4 1263 S 1791 0 1319 0 1371 6 1473 4 laFS 3 1527 6 1500 6 143s a 1600 9 INo! 1000 2 6 09679 I 1264 1 Mit i Stil I 6PM ieter iMM IJett t7N8 I AIF3 i Site 1 0050 1 9177 I tatt B 974 r th alm MM lelM IM 96 felM 395 96 405 W 995 M 005 W 796 M 895 56 905M 1986M 300 e 4 00070 7742 1 9173 2 0619 t itel 2 3709 flees 20756 3 0563 3 30s4 3 9s00 37MS 4 0007 47c7 4 4Fst lets 446 h 379 90 mil 1231 9 4267 e litt 9 1318 2 1378 I IU30 leM 9 1927 3 1500 4 163s ! 1608 F 1748 0 INGI L 6 &$732 i3330 It&73 1 9009 1 6100 1 6863 44030 1 7399 I FFH lilN 1 0000 1 8644 1 9:33 19sM 1 9732 h 47 N 97 70 ' IU 30 197 N M7 N M7 N 497 70 MF M 002 N 797 70 007 70 997 70 let? 70 PM e 0 06075 1 7108 10Mt 19Mt 2 1171 27mt 74074 2 7th 2 9tet 3 1006 3 4004 3aM9 3 essi 400st 430er 4407 0 9 4 363 M IN19 12N e IMit 1299 0 1317 % l370 5 1476 14M 6 1677 1 19N 8 ISM O 8600 6 IFelt leeB S s $5764 Ilit7 i Mit Itest i 6680 1 6806 44006 iFNS I H13 8 Oggt 1 0837 iSHI I 9000 i926 ieste D 30 93 0893 130 93 18093 200 93 30593 40893 500 93 000 93 Met) Nets 90093190893 300 e $$1000 IHel 1 465 19037 2 0322 ilMI 2 3909 1 6194 2 0437 3 006S 370M stest 3 F717 39M4 4 1543 061s th a 30717 1707 3 ItN S feet tree t IN60 lp00 8472 1 14Fe r nF60 lite t lost 1400 4 IN17 17998 6 SSN6 1 9146 1 9464 l5790 14003 1 6368 letal 1 7273 I Mit 100s3 1439% 197M 1 9090 I t3M 1 9649 $h M 7% M FS 13% PS 805 75 20% PS 30% 75 40% FS tel7% 405 M 70% 75 085 M SOS PS 1995 75 200 e 9 08005 Iltse I HIS 1 8377 9570 20F12 2 3058 ISM 9 2 7440 2 990S 31711 3 3874 3 5976 3 0019 4 0106 6s34 216 h N000 INf6 1777 3 12S8 9 700 1 8316 0 1369 % 1428 7 14739 ISN S 1579 6 1633 5 160B 7 1743 6 1799 P e elsee illM lasi2 8530

test I Mil 1 6700 172N I M30 10N3. 3 0394 1 9800 1 9010 8.Mie teste h

32 65 OfM 432M lef69 302 Sl 30f M 402$$ tafM 007SS 70f St N265 902 65 8002 66 800 e GM000 1 6s77 1626 1 7066 4 0003 700se 2233 tee 0F 2 6000 # 8986 3 084) 3 2000 14778 36M6 3 0764 1857Jll 6 303 99 120f 9 1775 7 129P 7 82072 lHS2 1300 t 1821 3 14736 ISIS 2 ISM 4 M33 3 1400 0 1743 4 iPet 6 e 48Mt 13106 llMI 1943 1453 ISIN 8 6750 11892 1 7901 6754 44317 4 0062 14072 197M l M72 h 39M 79H INN 379M 779M 379M 4P9H SMM $79p 779M 379H 979H 19796s 300 e 0 01004 1 4939 I543 1 7084 1 0733 8 9363 # IlN I 3000 tSMS 2 M90 f9844 3len 3 Hee 3 SDH 3 Met 1080 311 h 30P M 1201 2 IfM B IIM S 1206 3 IMal 1380 4 lamt 1473 3 3525 9 ilftr 1633 8 14070 IM33 1799 4 s Stelt latit LSall 1.9067 1 9000 1 8233 1 6719 1 7153 litM l>997 BAISO lasil ISOM 8 904 igm 6 h NM MM MM MM 276M SMM eMM SMM SNM 776M 376M 9M00 1976M 300 e tel099 1 4400 1 5707 1 6462 MP3 872) #0073 22083 f eart 26FM 2 0700 3 0670 37He 34430 3 6337 telaall b 40013 1803 4 1272 5 8256 2 205 3 313 7 1967 0 6430 1 M729 1925 6 1570 9 MN9 1807 6 17s3 1 47993 s 40006 140s8 3 6368 1 9642 1 9060 i 6itt 14000 1 7864 81586 1J000 10 pea 18679 14000 1 9306 le0N D 230f P302 lt302 8730f 273 02 373 02 473 02 573 02 673 02 773 02 073 02 973 07 1971 02 330 e 40153 l 40s0 leses 391) I Met t el?$ # 8860 ! ?l32 2 4054 # Mne 3 7076 79692 31585 3 H09 3 5777 ten 88 4 003 4 203 6 1220 9 iflee lies 4 1313 0 1573 I420 0 14F2 5 1975 3 1970 r IH27 160 S 37e2e iPtst s 40006 Lasti I 6283 inoe 15076 461H IGles i3079 8 7400 11065 IA300 iStes 4 0064 I 9178 I sees h fiel 79 01 Ifles lPitt 771 01 371 05 471 01 571 01 6710I 771 01 071 01 97101 50Fl es tot e 4 00000 1 3040 letti IlM9 1 8618 i F168 Mll f leu $ 33H filFl $ N00 2 0818 3 Nil 3 Pe02 3 4106 1830 905 h 4500 1203 0 1819 7 17W e l703 4 1817 1 306 7 8419 6 l477 7 4525 0 1978 4 IGN S 16073 1747 0 17900 t $956 l etts IllM 13676 33036 4 6314 4006 lj0se 174e5 IJeft I glM lalle letal stin 19:32 Sh 19 77 60 77 310 3F 4077 750 37 77 480 77 MS FF $4077 MG PF 080 77 Me)F Igsp?p 300 e 4 01981 3MS IJFPS 8 49:3 1 4007 pert IMM Gut 77MP # 444g 2 6719 3 7900 JerM 3 ell 3 370g 1438 735 b 40003 70s 0 1217 5 IMll 6702 4 Hl4 1346 2 #19 2 1471 0 1926 7 1970 2 1632 3 1687 1 1742 6 lite t s SONS 14966 13:19 Ile63 l.H97 0077 16HI BJ000 8 7411 BJMP label 1488 8 0700 1 9106 1 9s00 th 15 59 M St IS H 4959 269 50 allll 46199 MS H Ml 59 MS 59 MS H 965 59 Img 59 300 e SM#if 7091 3pel l ease , His 4WS l es78 207H 2 7009 2 3PH fle82 I 7l# 20M8 3 0%97 3 7719 14M ell t 417 01 708 1 til t 3:30 3 Psi l 316 6 536l 4 leas t 14F15 ISN 4 ISFF 9 16M t 1606 9 1742 % $ 790 8 9 00MI .49s1 9073 1 9444 ,lMS 4000 8 6536 IMM 1 7379 IJM4 lelM least telee 19073 4933 Sh it M 40 M le M et M MG M 360 M 460 M $40 39 HA M MG M 000 M tee n les0 M SOS e 8 01975 i ttle 1 7472 1 3806 463% MtB 17elt 191M 2 002$ ifeed telN tSite 2FM6 2MF 3 0512 18M 648 h 410 H 708 4 1287 4 1347 7 2 P9 ) 3M O IM45 64179 8476 8 llH 8 157F 4 1631 6 14es t 1747 17946 6 043M l4004 4 4982 llM0 ll4H HM lMM I Mit 1 731% S Mt2 14087 1 9304 14795 1 981 1947 $h = luteth00t. I h = Ovithalpy. Blu 00f Ib v = Sp0cific 904ume, tu 11 per Ib s = Sfitropy. Stu per R per Ib B -5

_,a i Table 3. Supeetlealed Sleem-Continered Abs Pless. LWSG in. $44. Set longerseers-Orrets feewenhal llet. Ionel W8107 Sleen egg 300 set 800 sse Me seg ges 1000 lies 1300 last 100s lies k. l 40 5640 106 40 Ill40 105 40 25540 MS 40 ell 40 SM..5 et Pil40 GH40 95540 leu 40 a. . title 116le i1730 870sa i 3a36 1 4763 3 M86 8 6499 I Sint I 9759 21339 2 7908 2 delt 2 MB7 2 lea 404 4 47457 87084 13 0 laell 12785 5367 4 Imt IM34 len.e 14701 0 00ftp lets7 8 e 1510t lull 4 5004 168U 1 6406 ISH 3 197 len t 9405 7 1741 9 179e 7 16 0 8 72t6 176M 37.690 4 0375 1 96s7 199H 3 9710 h. 80 M60 19060 t1960 78000 fitte 2000 elete H040 45040 790 00 050 60 95060 10W 40 410 SM982 Ilen 18078 '7646 13tl3 i e007 940 % IW6 17MS teMS 70304 23796 # N73 247M 7 6196 27ul 1000401 h 4f996 8 842M 8 4.e 7 8 4.& P IN 139 7W4 1754 '306 8 13M i un l ei.S IMP 3 8486 2 1469 4 ISn ; 1576 4 16300 iteit IMI6 1790 0 t 5306 IHW 163el 16793 17197 1 575 1 7937 leMS letti 3 0099 191M t i 45 97 tlU 14597 19697 Ml97 Mit7 44597 $8597 Mit? M19F $$197 9e597 l.elt? 1 est 0 01980 1 95S4 11587 I Pete 1331g l el30 l e976 16 eel 1 7910 1 9363 2 0790 72703 2 3605 2 4900 2 6304 late.eg 6 4M 77 1704 0 42M i 63734 130s I 1333 2 1361 1 1485 3 1400 7 lini 1575 9 1630 4 1605 5 IFel t i7977 8 84332 14759 8 5833 134M 8 57n 20000 I NGS 8 67M 3 7842 IJlli 11870 1 8286 10HS 1 9987 1 9143 4H th, elle tile Belle tile 78150 3elle 4elle 58150 Ml10 Mlle esite 9elle lealte 4 . 08900 f eet? letM l telt l Psel M82 3 43e7 1 5703 I FIIF leses 190n fl?M 2 7569 iMS3 2 57M 8894105 4 4M S3 latt e l2M 9 1279 3 130n 331 8 1300 0 1414 4 lette 16715 1575 4 86M 9 leell l7e0 9 tme i s 94387 4.4740 3 3000 ISett isnt 3082 1 6230 1 8400 8 7009 I Nel 8 70M 18165 8 0000 1847 1 9003 h. 37 8.

• 87le 3718 80740 737le 337II 43F10 53710 617le 737le N7le MFle 10p10 i

i 6 04967 0 9060 sett l 1300 2 170sl 1 3615 1 9073 5 6304 I nl6 1 9030 1 9330 2 1419 iMOS gain 3.11g 1325 1350 0 lent 14673 ISM 9 ISN 9 MMS Mes t IN06 17977 1882 078 h 4ea rt [Ns4 2M.0 t 1840 6 8.9.6 S terl alp 6 1 9870 1 7038 I Mit IJn7 8 0154 8400 ISMS 1 9085 5 SH3. 34HP A 1 5306 2 h. 37 90 SF 99 37 M 37 99 m 99 337 99 43799 532 99 437M 732M 032 99 932 M l.17 9t 300 0 0997}.9nt SMll 8 0799 lite 23n i30n Ie27 I USS I 6987 ISM 6 I 9907 f8746 7ien 23703 (- lIWGH h 409w 120e 7 Ifl IMF0 Mt1 379 I 1357 7 1417 7 1886 6 1130 3 4GN 4 t 49e00 84HO SA.a t 167 I 4.H00 5905

S 078 8 6423 1 6670 10000 41378 iv30 13.9I legse ING3 nts 9 0 1 8303 1 8307 3 Otte

.M.93 i.0 93 n.93 nm im.3 370 93 7 120 170 93 270 9 478 9,35f893 0f0 .00. . 09 4 6 i i it iam n.93 710,93. 0 93 9,N 93 10,70 93 IUt til 4 elele 170s1 i i t e6 nMS 173 IMe0 1797e 43M P 13% $ laiI O tem 9 1919 7 lin m, 14.03 1 1U3 1678 7 Nee 0 8 Setet 1 4001 3 4 5273 I Stat lleet 19077 gent lages 8 7325 8JI.9 87 1794 7 Im INe8 1.40H 100M 4 h. .M 99.M.99 IN.99 i IP4 9,9ma i.nl.9.n e 27e 9 3f499 4M.99 SN M.OM.M 7f8 9,0 Gre.M,9Pe 99 1,974 99 ... Omn 9 9 im.i inn 8 1 = 0H . ann me. IIM I io,i Im 1 0 i tte, i t. n.a n. .m l m imi mle IA3 sSM4 1 Seel laes Is.3 44.9 8esti i FNs t 76et i 7908 10.6 =0 M nM, 6 j e 30907 4 416l 3 b IISIS I Stil . h. .P.l M.Pt 16 i li.t M lil 774 4 478 56 MI4 1 n is.86 371 M, Ut.16 778 M WI.il 97116 19,71.M. .00 04 u 9eM i m,7 im i Mn imt it .n =,0 10 n Out t.1 . eu w nOs, im t i=3 i 9 i 9 im =0 me e mel Mnl Moi nMe imi 0 00M8 ieut Iene iH06 i M3B I 5717 I NPS IM38 86053 3 nu I7100 1 7939 ISM 3 iSSn Ies/0 .n.o, 091.n u n, im.i im 0.o .,,o mu m.u mu mu mo n,.n m.o,n.uMn,o 1 0 S Mn. n.4 4 nin n ipn I im in inn om. Mni ni S i I I sn o in 00m n.n. a.i m. m.n 8 7 mn mt Mn =9 nMI im, n =0 n u inn um i.n h. ..On .M. 1300.M ID 11300 M o.n i a.ttinn IMn.i=>ieue m. Im. Filst 38300 49 um n= i.3 00 St.l. 681. fl198 tilt 0 91100 l.n.te 9. e 0786 eleN l.9 e 1 i ol.l om a me n.'! inn. I'.M.9 i t.t it no 74 nnt im =6 .n.M.Sn6 im a imi ns nm im7 i=0 nM 1 gb 5 07 8 .nh1 .$.5 88

1. lt

.e.IM il9m AII na n.lt te.llt los n.l.l lee,l li 306 18 del 809 11 30 00519 Sti 0"[I I"! I"t l'."1 IW IW IE l*ast IW l'al [,g i.598 4 1 9 9-1 0n t'/ M n I W I"mlil l'#0! 1"/.! 3

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O.ne ne.le om. 10 im6 m Im.3 i.=.0 i m., i n,8,, 1. um ene ina 4.i t noe m nu 0 unt inn n.n i4M n n i7m i,e. i lu M n inie 4.l.3 n i= n .m.e 4.m.i6. 0 0.M im s is 4 .9 .94. il 0 i4 .4 n i.t.4 .,0.,9 0 9%, .til, . 9 14 6 nn 7 9 .9 i n m i.=,3.um nnt .M t.l 9 i nM9 imi im7 I. n it ( U6 an9 i n ime nM. n9a e E7WI i42M l e300 149n i1796 i M n i8065 8 6494 I 6006 1.7262 1 7900 179M I etM i M38 l i Sh 38 79 01 79 ms.Ill't.808 79 Pet 79 301 79 ell 79 SGI 79 et Ml P9 081 79 981 79 MO . ee F eues ml nm 1.t 79 1 S40 fH h 100 03 nM4 8710 1 1770 1 83 ? 7m um enn lum n 3 von l=9 lu6 j e .7ill 1 4163 leen 44 9 1 5898 1 6400 1 9000 8 13M 3 Inti B.lle Illi e 198 9 16n 7 1678 9 87M P 17979 t te 83 88 7 13175 Inti 1 7064 t ales IOMs th .M 76 N 76.IN M IN 76 f p4 P6 3N F4 4N M SM 76 674 f4 794 76 874 86 9M M 000 . 40tlM.53M us! 06M6 6079 6 7315 $ WOS 998p 89c0 3 0806 a lles 17111 8 7055 I Mas OmalM h H040 1:00 0 gn30 IMst 1307 s 13M 0 15.6 lesse 15800 lusi lult M76 0 nie t im3 n9 6 9 PlW l 4006 14M7 14M3 8liet a306 9 4 63M i 6733 l1887 iNte i1700 100M i 0395 l D, 10 M 68 05 ll0M 140 M fleM 36sM 460 95 MG M 080 05 MG M MGM 960 05 8H 00Pl?3 O ne09 OSM3 nent 06M8 0 6090 0 7183 Seite 9 9 9990 197N llem 17H1 I ?8M Sal HI h $M 70 ltM 4 !!!$ 5 lMS6 17986 lH77 17904 14%7 2 11.M7 5 1964 4 IN06 86771 IFM I 17986 8 9 7279 14NI Ien) 4out i 1080 1 6311 IMn 162H I 6462 4 3033 1last Inla 300F8 IOut i Sh = Supe #hett, f h = enthalpy. Stu per lh { V = Specilec 904 ems, to fI per ab 8 =.atrSpy, Blu per f per it B-6

. ~.. _ _. _ _ ~. _ .s .i = I. + 1 Tehte 3. Superheeled Sleam-Contmoed Aes Peets. tel$g la $el - Set feaisteelse-Deseeet 7threaneet 4 ,1141. Iestel Walee $leem $$$ GN NG - PW )$$ W $$$ 910 M 11N 13N ' 13N 14N litt th 11 68 61 61 111 61 161 61 til 68 MI 61 311 68 Elli del St M1ll 06868 M1ll all el Mi St WI o eWiel 04721 04W3 0 9406 et993 eteet 0 6078 0FH2 0 7656 eStas 08753 0 9855 l ole! 18037 1 8484 12:43 Sat 3ll & SM 7e lite 7 12376 IMSI 17984 13M 3 IMI% IMP 0 lef t S late 3 1947 0 1963 2 1689 S 86 4 i till 3 1M13 i ] s 47MS IMIS I4000 ie967 1 4971 8 W20 4 MOS ISMS I HF7 4 6893 1 6905 I 6967 I 7387 8 Met i7MS I 42H h 50 llet tel47 IH 47 2e5e7 FM42 30547 5542 ellet Mle2 H542 755 4 M187 MS 42 30I0 e GWitt edelt tellt ell 37 GMM e400e e6est 96875 077e5 07es3 0 8795 0 0954 996n leite 1 9301 I lt:0 Gee 301 h 182M lit? 9 18993 IN93 1790 l 13M 9 IneF Ilet6 le19 e less t 1986 4 4168 9 1614 4 147s 1 t 712 5 l793I s mMM iMle iJ973 14467 4 4833 8 5149 i M26 I MF7 IS40 164M ! 6630 iSept IFM6 8 7509 8 7905 1 8:47 D eter 9947 14947 19947 M947 7934F Mt47 44947 54947 4e947 74987 Ge947 94947 IMO e $WIPP 9 077 04071 0 5312 elPe1 0614 e6515 0 4872 0 7716 9 7081 0 8124 still 09M7 1 8373 I C973 Stel39 h MG15 litt 4 1243e 1757 IMP 4 13MI IMF2 1817 3 last 6 1983 9 1940 7 161F 4 1674 4 8738 6 1769 6 6 Efte7 1JNI I4Me 14F48 8 5e77 I 5364 i M00 1504 1 4062 84469 3 6885 1 7197 8 1538 8 1986 i Sill th 4377 93 72 143 72 193 77 Pa3 72 M3 72 M3 72 443 72 nel77 64372 743 77 M3 F2 943 ?? 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8 1396 82794 13J74 1 3007 Ielle ise64 1 4730 i 8976 1 5203 I Wit 1 Mll 168 H I 6616 sige teste 8044% 4 1193 0 1167 Silo 0164F 0 1769 0 1883 0 1993 O M93 O NIP 0 ?8 70 0 768% b twl 1858 6 Inst 13en s IMit Imo nelli le 7t l 1517 7 1976 1616 1 1687 6 17ss e s 1 9306 iFH4 lNH I J606 8 4053 14Je6 1 4642 1 4093 1 1824 1SMI a list i 6809 8 6467 th sees e 9 0471 0 0886 0809 0 1770 0 14?0 em 0 1671 0 1781 0 1847 O l**6 0 7174 0FMI O Mit n 909 % H 77,) In)) 1789 9 1H70 IMe 14804 1869 r 15071 4W30 16i7 3 1679 4 174 4 e leH6 Inn I J07J 63M6 139e9 l a27 l esM 1 446; 4 5684 I W64 I M73 160e4 lust $h a superheat.F h = enthalpy. Blu per Ib v = Specific teleme, tu 11 per lti s = entropy, Blu per R per 16 B-8 -__.__._.---,-u

Tallie 3. Superhealed Steam-Continued Aes Press. lb/Se la. Set 1st I"8alure-Der'eet f atweelicil 15at. Iemel watee Steam 750 000 ese see ese Ites late list line 1788 1250 1300 lose 150s . 3. . mi ei .ii..im Oi S t i...n S n.. i.,. l. . M Fi Ono.NM h 534 1100 4 8207 3 lU72 13J2 6 1300 5 5423 7 1463 9 1501 9 1534 4 1573 4 1000 5 16763 6747 7 s 1 9331 130e4 1 2922 IJe46 lJ047 1 4181 leen 147M 5 49N l.5497 1 5407 8 5607 1 5902 163M th i 'es6 'N fkl !3i 'l3'F$ 4l !a'$so !M f5 !S'6D !N !67'3$ !74 n e I 0 s 4.0180 183% JMS 8J32 IJ745 4098 44MO I 4457 149el I $128 1J341 1 M43 I H2n I W12 Sh, Jent Se3M 9591 8005$ eleM siles 01317 eleM elSM el6M 0 1718 ele 06 e le90 0 20$0 en03 h e54 9 le879 l173 6 IM29 I?t35 IM46 1410 7 14$2 5 1491 5 15291 IS6S S 1600 9 16F00 17374 s I N79 8.8553 IJ612 1 3207 kJ645 44006 143N 3 4542 1 4838 1.5068 1.52H 1 5441 1.5063 I Wis th Spel e 083M S el31 te7N SMF3 0 1119 0 t744 0 8356 8 8458 O!M3 0 1642 0148 ettle 01966 0 7114 h esS 4 8e86 9 llH0 IN04 13837 13M 6 1483 4 leas t 1406 3 JU4% 1561 3 IS972 IE68 1047 s 0 990S I 13M 4 24 % 8 3005 8 3 lot i30l( l42M i 4500 1 4762 8 4996 I W14 1J420 1 5006 I 6ill th, test ee317 0esas 007M eSel! e 1958 e it87 9 1797 9IM2 e leal eIS7? eitse e17M 0less eM3: h UsS 994 3 1834 6 1727 7 IM37 IM84 1396 S 1440 3 last i 1519 e luF I Inje 1663 7 lin I s t9815 l 1875 12296 IJ9tl B 3446 IJ827 1.4158 1 4437 8.4691 1 4931 i S!$3 4 S362 i S750 1 6100 Sh 1000 e 8 4300 ees47 ee677 8teu e10el e it74 ein2 0IMI 0 1877 0 lies 0ISet 0 iS57 0 1815 e 1954 h 432 4 975 0 1819 9 1214 8 8283 7 1M42 13M 6 1434 3 1475 9 1515 2 IH29 85494 ISOS 87?9 % 8 8 98S5 1 8908 12137 IJSSO IJMs IJ74 1.4075 44M6 4 4628 1459 I S003 I S30s 1 9697 1 6054 th sees e see3 e'0419 easn seen eenet 0 :0F0 esin el?P4 e:M3 e i447 eivt else) e lF47 O iasi t ePF 3 954 8 1161 8 IMit P773 6 1317 0 IM76 547e 3 1470 6 1514 % 1987 1545 4 16%7 4 177r. a s SNU l N67 llM1 IJ7N 3 3250 l 3658 1J999 8 4217 I4M4 140m I58JS I Siet i M44 1 teen 3 ..ut . m,. 0. iOM. iiM. in, D i .iMi.i 012. O il. O f.i, t 872 9 9458 1984 6 4888 0 IM34 IN36 1375 7 1U23 14654 150$9 1946 15870 1654 2 1724 2 s 0 9758 1 9746 1 8433 S Mll IJIM IJSF4 8325 IUM 1 4900 1 4748 1 8978 8.SIM 1 993 8.M60 m HIS e 4GPSF 40M4 004M 0 06 % 0 0793 0 0000 0 1012 elles tilts Ot?t6 0 1340 0 1411 0 1544 0 1669 h 313 9 919 5 1984 7 IIM 3 12374 1302 7 1358 1 14073 14S2 7 1494 2 IS341 ISF7 % 1646 4 17176 5 0Nel I OSil i 1506 8JNS I M17 IJHO IJ743 i esu 8 4347 14008 1 4843 i Seu I 5418 i Moe D 3ete o 0 4779 003M S tem O OST) 0 9764 G eB16 0 9915 0 100* 01 05 01160 0 1731 O l?*8 0 8474 O ISO h 086 9 906 8 1916 % llN 9 1212 6 1701 7 IMOS IM77 1439 1 1462 6 1573 7 IM31 8638 6 17111 6 0 # 42 lGM0 1 1243 8.MH IJ600 1 3173 1.3567 8 3904 8.42W l.4446 8 4780 149M 1 S3% i S73% In ION e 90FFF 0 0318 0 8399 8512 0 0831 0 9737 0 0833 Seelt 9 0096 tielt ellM 9 1700 0 1171 Olen b Wla 009 0 997 9 18D7 ) l186 3 IMit 13229 INF2 lette 14710 1513 3 IM37 1630 4 17046 s t#14 1 524 1 3033 8.6418 3 2473 1J000 IJ397 8 37S4 8 4059 3 43M i 4Se6 8 4019 4 Wel 1 % 32 Sh 8001 o 0 0767 003e6 00HI 9 086% 0 0%F1 0 0671 6 0762 0 0845 t otM 8 8006 0 1054 g illi 0100 OlH8 1974 1145 4 1241 0 130S % lM27 14s10 14H 6 IS031 Iwat lull 1699 :. h 796 6 479 1 914 4 1.168) 4 I n71 l tits l M13 1 M43 lJON 4 4208 4 4467 1 4705 l S140 i H33 t 0 94 % I till I N64 th 0 876{ 0 0796 SOMO 9 0s19 soln 00615 0 0F01 0 0FW 0 0853 S Mit 0 0887 0 1881 Silla 017Se 1000 v M9 10W S Il44 0 8171 9 1280 % IMFS 8400 F less 2 1497 9 ISM 3 86tl4 1691 7 b 792 a 47I 2 8 872)i ! 8437 IJeet 8 2627 l Je76 8.M60 1379J B 4087 14JS2 3 4597 8 5040 t ten 8 Steet 1 0037 i th less .e S t>S8 0 0780 00HS 9 0402 0 0453 0 0564 O sset 0 0774 00794 0 00S4 Omit S MFS SIMI 0 1179 i h FH 3 e64 7 944 0 10374 IBM 4 8204 1 IU21 4H30 IM7I 84371 14s2 9 lu6a 1607 9 1681 3 8 09M4 0 9064 iM13 1.lMS 8 1918 12464 IMM 43N3 IJ667 IJt70 14243 144W 1 8944 ISM 9 sh 9000 e 0 0754 0 07e7 Sout 003a0 e 0451 00Sfs esse) 0 06FS 8 0747 e se64 ese67 00 57 0 1019 elll3 h Fe64 819 7 9M3 19734 110e 9 11877 47M 6 Ilit t 137S t 1476 1 1471 8 85171 IWitt e 1674 0 l 6 4 9310 8 9900 1 9566 t ill3 1.1778 123M 12785 1 3198 1 3546 13054 14137 14M2 1 8458 B W63 sh 18888 e G OPSI 8 0775 0 0317 00M7 ODOS 8 0895 00HS 0 0633 0 08U 0 0757 0 0017 00s0 0 0063 0 8054 h 7818 $$4 5 910 7 8011 3 1094 7 1l44 1742 0 130$ 3 BM29 1415 3 44534 Iwe6 IM11 1677 8 0 0 N10 0 9642 1 0432 i LOM I 46M ilist iMW I J065 iMM i 3749 8 403S 4 495 1 4763 1 Sl63 sh lette 0 8748 0 07F1 00M3 0 0347 00ses 0 0467 00Sn 005M 0 0696 0 0784 0 0764 0 0818 0 0813 0 1001 l t F91 % OSO S 9De 80D10 leel l 185e 9 Inge I?92 4 IMll 1404 F 1413 9 IS000 HOS I 16.6 7 t 0NN 4 9790 i SJS4 I ODM i blit i 2060 12SM i 2946 1 3371 1 Med 1MN I 4202 5 4677 8 5100 i Sh = superheat. F h = enthalpy. Bfu per Ib y a specific volume, tu fl per ib 5 = entrosy, Blu per F per Ib l l l I l 8 -9 l --

Table 3. Superhealed Slesm-Confiaved Aos Prest tW5e la. Sal Sal I**e"atuee - 0eeeees tahecaneil 15al. Ismol water stea a pse see ese see see Ices tels lles ille 17ee 1250 130s late flee llege e eer45 ee47 0 e716 e03M eeles eesas emas esul emM e e616 e e777 e 0776 eesas eee7 6 779 % es69 9175 M7I lett 9 4446 3 tilSt 87e87 53M 7 13944 1444 6 1491 5 15747 86As 6 s e 9196 8 9747 1 eP97 I Wil i 1417 1 1946 1 2414 IFeM I37ee 13bes a 3847 I ell? I 4596 i Se73 tttte ser43 eers) seres ee.i+5 ses7e sosis ses78 eMM esses sesal e sti s e75 ser'; co9et a nF7 essa 904 9es t lett e llM9 17e4 3 eMe7 170e s lass e 14Ms 1443r Is78e 16s47 S e9163 eNW IeP32 8 8772 1 1316 Ilede 123# I U27 1 3107 I 3s46 8373e 14875 1 451% i 4949 lasse e eer48 ee7ee eeres e esl> een) eenen eesu ee5ne emee eele eelst e07es es7te eeast a n61 est e 9es t 9n e 1050 9 at:4 5 1193 7 IMas lanes 1374 7 lens len t swe9 164e s s etill e 9657 i elf t i e7el IuM i 1742 112ee aMn 1Jele 13353 I as42 1.Jost i esM ies77 1 les tw3e earu se'79 easet seM6 sene seen esses can esses peut em's 0e756 east; h Her e3e 6 W39 974 9 les31 lln g lita l 1747 9 13 ell 13654 141ee 14677 IH47 16834 s etiel e#4e Iel27 1 537 1 1858 1 1653 i Filt i25M 1191e aJ7H 1.35 4 13ees a4M3 1eset Lee 8 IePM ewSI eenn eeier 001M e 014 ees4 eeste eMIF eeHe 0ese? Ienel e0775 e 8799 i h Hil eMI 1one %44 leM 7 lleL F Bl74 8 8738 5 IPP6 IM6% 14n9 6 14M 4 IH16 16374 ( 6 etail ethel 1nm 1 M78 1 IGM i 1971 1 M39 I Men 1Je31 IalM i M9e 137el I 4791 1 4748 i lasse e eePM e0751 e ePil e art 7 ee370 eeMe eesel ees48 e 0897 eMM ee577 eesit ee696 ee764 h Hf3 SM4 seit 962 7 leMe lettl 1866 3 1279 7 IMie IMel 1401 5 leSi t Ital 7 16319 s e test e 9548 I esH 1.e24 1 1914 8 left i19se iFMI 11749 130es 13sil 1 3705 1 4273 1 4671 14000 ee733 ee748 Ie?67 ee791 e e3M eeM4 ee397 ees32 ees74 eell5 EMS $ e e595 ee67e ee740 t Fil 3 SML 394 3 954e le745 let? 3 inei !U!4 1783 0 13se 2 IM38 lose 4 IS3e a 16M S ) eSeit e9585 e 99W I e873 8 esS3 1 1426 81872 112L' IJ678 8 Jell I 33M 1 3631 1 4153 1 4612 loses e se238 se746 0 97t4 J 2787 Selle essal se3N soste oeste ses96 eelM eMP3 8 0444 0 0714 He4 631 e ell 7 hel teltl 8086 7 Illt e 12139 INS 4 11M 9 13e64 14373 ISUS 1878 1 8 e e994 e 9ses e 9957 i esM i se97 IIM2 8 1883 IFNs i M97 8 29e9 83M6 1354e 8ee87 i enti liese se*3e se744 semi ester esses oesp eeM9 esse ses43 easM s pill oms 2 c osN e ssM M16 479 S set 3 The 9 10l%i lese 6 1144 9 1706 8 IMei IU6e 33794 1430 3 lit 6 4 1615 9 s e097e e tsSS e 9920 I e387 iese6 1 1302 IIFM 1 Plat i M25 1 2000 1 3897 i M98 14e22 3 449s I lesse e serie seter eene ear 7e esser e s3M esses eeM3 easM sessa esset essM se6e ess6s n Mal est seit gets Relin isn t line uen3 IMll 13its isFra lens luce asses s e Ms6 e ts77 e1846 I e34e I e797 1 1747 1 1674 i M73 i NS7 12elt i 3131 1 3424 1 3959 8 4413 Sh = supetheel. I h = entileipy. Stu per Ib e = specils volume, tu fl per Ib s = entropy.Stu per R per ib I l e B-10

W.t.. .W.i a s = ,,n .j y. [, set #Is t y ,,j.g "l ii c. ,n.t ..,,...l ._ $ dP -, shl!' 0 4 F.'.:'i j g(u'lui!hM I}D P' F !gjp

qjy tr a

]!!i:M YiM T ~il if li!":.6il9JN Umd ,t 'i ih6 1.M NWifi NIMi wm

. qr I@.%.,~n. w-. ~.w

. -,tl.,

n n..A.t.;,:t,. =

1. '?iU J: '

'H! b>. p .y .. l' h .~m.lft.. YtY$ % NT g., a.

1. FN. av i

.2-wyH~ue ~ -r. - m y JS'J a,[ir:w#rDJk! b

8dh, u.

w m pr .)1 , 't. :P r, it.l% v . Tr& i V = r n yn u n- ~ L. S un j s! im .. M,,mm,,m,, ngg- +e.,ms n n ,~p ,t tf I qsga g w+.< m - m an --l g ~4 .+ _m,, 1 ,n p ,x n. y, p, u w%, v s. 1 q v-% v,&m n ? . in,s _m, $I'h b.[. j fJ lHisKbTSNErMGMtl$ r h 2 ' f ~ .;, yf t rtl.I,y (.'. p n / r . t. j 7 p .vg ccr V u., =..e.W k.s&m "M + ,w Ai &WasL"h* ? ,'***W,,. h+ M +M * .... x,r.? .kfN k M M.d*DYNmN.MY,N_S M =n w*u,m %g. [f)k 4.

J Y,-Hw.At

.a Rha!7,f" ,,g + sy .MJ:!*,**,,._ gn% _ _ ga: av t-,- ,m u , F, h'Q 'cf: Q.:M:W ~ H --e+r.4.f i.' ' w&. :6~ f*&++z.,i;a ?[y " ~ p W :_. m y,a;. '

8.b

.%

M i g n~=.tQ, Mpm ,.;g' ..g ...n k,*,=ATi [ [ eM.. 2f[ Y [4;+[. j{r'- .,. "m3# w. = ~ w.n.., y9.,::,'g;a J9 ,, a 7, e r.2m.,.e.o,. - .2:=e-eM'=-N..,;,. ;e:.. fe rA.: +rt -r+r.-.. kh"#Ji !J% * , f@& y@f B ,, 'WY Fd i. % d yfi2t@y.$/ ?f = i&h Y.U = ingP'-]~ ,6i'i yg j9 -dwm: 46 m uni e,em [.iN,-}h...b!![;[q,!fiMdY h -h 4(.;.hN..}I" p a. e h, 7,.[h[z[5[#.s!I ,k,..,,(g,.t

• Il

_M .n .,,*,~ vl. n.... fY,

b. : i*

d ad. :tl'*'d g).)y4,"r'Q. . :.?= d' 9 f;, ,,t; fr ; w n e .y' fiVi;r }t, a s N._e f e-3,T30PT

• ' '1; PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 17 THERMDDTNAMICS, HEAT TRAN5FER AND FLUID FLOW ANSWERS -- KEWAUNEE

-87/02/17-VICTOR,F. ANSWER 1.01 (1.00) Temperature is 328 degrees F +/- 1. (0,5) The fluid will be saturated (wet vapor state since this is a throttling process). (0.5) REFERENCE CNTO Thermal-Hydraulics Principles p.10-62 to 10-72 Steam Tables and/or Mollier diagram ANSWER 1.02 (2.00) 1. DNBR Decreases 2. DNBR Decreases 3. DNBR Increases 4. DNBR Decreases (0.5 each) (2.0) REFERENCE CNTO Thermal-Hydraulics Principles p.13-23 ANSWER 1.03 (2.00) i An elbow flow meter is used for this measurement.(0.5) The principle of { operation is based on fluid flow around the bend in the elbow which exerts force on the outside of the pipe radius.(0.5) This results in an increase in the pressure at the outside and a decreased pressure at the inside of 6 the radius.(0.5) Flow rate is determined by measuring the pressure differential.(0.5) (The volume flow rate is proportional to the square root of the pressure difference.) (2.0) REFERENCE CNTO Thermal-Hydraulic Principles p.11-23,11-24 t

---

r---,-------r-vw-------

'1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 18 THERMDDTNAMIC5, HEAT TRANSFER AND FLUID FLDW ANSWERS -- KEWAUNEE -87/02/17-VICTOR,F. ANSWER 1.04 (2.00)

a. Decrease. (.25) Available NPSH is a function of static pressure of the fluid. Reducing the vertical distance between the tank and the pump decreases the static pressure.(.75)

(1.0)

b. Increase. (.25) Cooling the fluid decreases the saturation pressure of the fluid, which increases available NPSH.(.75)

(1.0) (Similar wording acceptable) REFERENCE CNTO Thermal-Hydraulic Principles p. 10-60, 10-61 ANSWER 1.05 (2.00)

a. ACP Higher than ECP.

b. ACP Higher than ECP.

c. ACP Higher than ECP.

d. ACP Lower than ECP.

(0.5 each) (2.0) REFERENCE CNTO Core Control p.7-25 ANSWER 1.06 (2.00)

1. Gap thennal conductivity

2. Fuel densification

3. Cladding creep

4. Plutonium production (0.4 each)

Cladding creep (fuel clad gap reduction) is the most dominant effect(0.4) (2.0) The buhp of Pu -240 is also accepted as a corred answer REFERENCE Kewaunee Operator TM p. I-6.14 l l

' ' ' 1.' PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 19 THERP0 DYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- KEWAUNEE -87/02/17-VICTOR,F. ANSWER 1.07 (1.00) At 78 steps the total pcm in the rods is 600 pcm on the Integral Rod Worth curve.(0.4) Subtracting 250 pcm gives 350 pcm (0.2).At this value, D-bank is about 128 steps plus or minus 4 steps. (0.4) (1.0) REFERENCE CNTO Core Control p.6-16 to 6-21; Rx Data Book fig.5.2.1 ANSWER 1.08 (1.00) 130 seconds plus or minus 2 seconds P = Po10 Exp(sur)t P/Po = 1.4x10E-8 / 0.4 x 10E-8 = 3.5 (0.5) log (base 10) 3.5 = (0.25)t, t = 2.18 minutes (0.5) REFERENCE Kewaunee Operator TM p.I-5.13 ANSWER 1.09 (1.50) a. 1647 psig +/- 7 psig b. 642 psig +/- 7 psig (0.75 each) (1.5) REFERENCE ~ Steam Tables

'1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 20 THERMDDYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- KEWAUNEE -87/02/17-VICTOR,F. ANSWER 1.10 (1.50) S/G heat transfer = Q = UA(Tavg - Tstm) Q, U, and Tstm remain constant; A1(Tavg1 - Tsta) = A2(Tavg2 - Tstm) (0.50) GIVEN: A2 = 0.9 X Al From Steam Tables: Tsat for 750 psia = 511 F (0.50) A1(562 - 511) = 0.9A1(Tavg2 - 511) Tavg2 = 567.6 F (567 to 568.5 F acceptable) (0.50) REFERENCE CNTO Thermal-Hydraulic Principles, Ch.12, p.8 ANSWER 1.11 (1.50) Increases.(0.5) The moderator becomes less dense as temperature increases which allows neutrons to travel further before interacting with water molecules.(0.5) Therefore there is a higher probability of reaching a control rod which increases rod worth.(0.5) (1.5) REFERENCE CNTO Core Control p.6-22, 6-23 ANSWER 1.12 (2.50) a. 1. Void coefficient (0.4 each, 0.3 for correct order) 2. Moderator temperature coefficient 3. Doppler power (or fuel temperature) coefficient (1.5) b. Total power coefficient becomes more negative from BOL to E0L. (1.0) PieERENCE CNTO Core Control, P.3-29 TO 3-41 l

.c .l \\, s '1. PRINCIPLES OF NUCLEAR POWER PLAKT OPERATION, PAGE 21' THERMDDYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. r \\ 0 g< s ANSWER 1.13 (2.50) i$ .] i e y t e

a. Xenon is produced by fission (.25)'and Iodine. decay (.25) N J~

Xenon is removed by neutron absorptfon (.25) ar.d Xenon decay (.25) ' ] (1.0)

b. Samarium is produced by Promethium decay (.25) sad removed by neitron (7

s car @tre (.25) N. (0.5)

c. Xcton will peak (.25) and then decrease to'a new equilibrium below the innial value (.25)

(0.5) '? > Sadiarium will peak (.25) and then return to$he inith1 value (.25) (0.5) V i' REFERENCE s. CNTO CORE CONTROL p.4-26 to 4-35 L: g , tu t 2. .ti ANSWER 1.14 (2.50)

a. SDM is defined as the amount by which tM mctor core wouldde' J,

subcritical (.25) at hot shutdown conditions if all 'ccatrol rods were tripped,(.25) assuming that the liighest worth control rod ' t. remained fully withdrawn,(.25) and assuming no cha'rge in Xenon, f ( 1._0) \\ 5 or boron.(.25) 3 .g. b.1. To limit the consequences of a hypothetica' roa eject accident.(0.5) l

2. Assure adequate trip reactivity.

(0.5)

3. Assure meeting power distribution limits.

(0.5) ( 't \\ REFERENCE Technical Specifications p.TS 3.10-1, p.TS 3.10-8 t r ' li 1 -.---------,-------,,-------,-,,,,n- -,-,-----,-~--,--a

l 2.' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 22 t ANSWERS -- KEWAUNEE \\ -87/02/17-VICTOR,F. t 4 R ) ANSWER 2.01 i '(1.50.) 4; 9 1.BASTtoBATP(0.2)ther.(toFCY110A(0.1)thentoblender(0.1)then to outlet of VCT.(0.1) 3

2. BAST to BATP(0.2) to charging pump suction (0.1) via CVC-440.(0.2) s 3. BAST to BATP(0.2) to FCV 110A(0.1) to manual valve CVC-405.(0.2) (1.5)

{' 1 JAZFERENCE 'l KEWAUNEE OP No. E-CVC-35; D'AG. No. XK100-3G-X and XK100-38-H .4 ANSWER 2.02 41.50)

a. 1.

Reduce general corrosion (by reducing free oxygen).(0.25) 2. Scavenges dissolved oxygen at low temperature.(0.25) z' 3. Added to raise pH (at EOL when boric acid concentration is low and production of Li from neutron boron reaction is low). (0 25) 4. Addad to assist in purging the RCS of hydrogen.(0.25) (1.0) or acis a cover gas for %s. boip unws b.Chemicalsa/as .1 flushed from the mixing tank by reactor makeup water (0.1) which flows through the tank inlet line and passes the tank content to the suction of the Charging Pump.(0.2) Flow rate is controlled by an orifice located in the tank inlet line.(.2) (0.5) y w s REFERENCE KEWAUNEE 0D No. 35 p.3,12,24, Dwg yaco-31.p s, b 'h 1 4, $ lO ANSWER 2.03 (2.00) I 'U

a. False

\\'

b. True

c. False

d. True (0.5 each)

(2.0) t REFERENCE ( KEWAUNEE SD No.1 p. 2,3,6,9 l l l l

2.' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 23 ANSWERS -- KEWAUNEE -87/02/17-VICTOR,F. ANSWER 2.04 (2.50) (a) Component Cooling Water (b) Cosponent Cooling Water ~ (c) Service Watar (d) C:.-; :: t Ceclia; Weter Air Cooled (el" Reactor Makeup Water (0.5 each) (2.5) REFERENCE (a) KEWAUNEE SD No.33 p.4 (b) KEWAUNEE OP No N-CYC-35E (c) KEWAUNEE SD No. O p.2 (d) KEWAUNEE SD No. 31 p.2 Dg XKloO-36, m-wg (e) KEWAUNEE SD No. 36 p.8 ANSWER 2.05 (1.50)

a. Loss of Coolant; Steam Generator Tube Rupture; Loss of Secondary Cooling (0.25 each)

(0.75)

b. To prevent thermal shock (0.25) to the reactor nozzles (0.25) if the Safety Injection system is inadvertently activated.(0.25)

(0.75) REFERENCE KEWAUNEE SD No. 33 p.1 and 3 ANSWER 2.06 (1.50)

1. High-high steam flow coincident with SI signal.(0.25) Individual.(0.25)

2. High steam flow coincident with lo-lo Tavg (540 F) and SI signal.(0.25)

Individual.(0.25)

3. Hig -high containment pressure of(17 psig)(0.25) Both.(0.25)

REFERENCE KEWAUNEE SD No. 6 p.6 ( a.,,v+ ..%%m- ,,---,,,y. -,,_y _e q,_-p ,9,,,_.+ m

..j. .] W,i.,,. 2." PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 24 t ANSWERS -- KEWAUNEE -87/02/17-VICTOR,F. ANSWER 2.07 (2.50)

a. The NORMAL supply is the 7.5 KVA Inverter.(0.2) The 7.5 KVA Inverter, NORMAL supply is MCC 1-52C.(0.2) The 7.5 KVA Inverter STAND-BY supply is the Battery (BRA-101)(0.2) which is supplied from the Battery Charger (BRA-108)(0.2) which is powered from MCC 1-52C.(0.2)

The STAND-BY (ALTERNATE) supply for Instrument Bus No.IV is the AC Power Distrubution Cabinet (BRA-105)(0.2) which is supplied from a 480 V to 208/120 V transformer (0.2) normally supplied from MCC 1-52C (0.2) through a transfer switch.(0.2) The alternate source to the transfer switch is MCC 1-52E.(0.2) (2.0)

b. The breakers in Instrument Bus IV power cabinet are MECHANICALLY interlocked so only one can be closed.

(0,5) i i REFERENCE KEWAUNEE SD Mo. 38 p.2 to 12 and DWG-E233 L ANSWER 2.08 (2.50) a.1. Protects the pump against excessive temperature during low flow conditions.

2. Provides cooling water for pump bearing lube oil cooler.

3. Provides cooling water for the turbine drive bearing cooler.

(0.5 each) (1.5)

b. Service water suction supplying AFW Pump 1A is lost.(0.25) AFW pump 18 a

which is supplied from Service Water Train B(0.25) and the TDAFW pump which is supplied by both Service Water Trains.(0.25) are not affected. The TDAFW pump and AFW pump 1B can supply both steam generators.(0.25) (1.0) REFERENCE KEWAUNEE SD No. 58 p.2 and DWG M202 ANSWER 2.09 (1.50) i

a. 1. RWST l

2. BAST l

3. RHR pump discharge (Sumps)

The BAST is the first source to inject. (0.25 each) (1.0)

b. Check valves are installed in the SI line near the RCS loops.

(0.5) ,..-..~,_....__._.._.,___.-,__._..,,_,,,,__.._m,-... m,

' 2.* PLANT DESIGN INCLUDING SAFETY AND EERGENCY SYSTEMS PAGE 25 ANSERS -- KEWAUNEE -87/02/17-VICTOR, F. REFERENCE KEWAUNEE SD No. 33 p.3 and p.5,6 ANSWER 2.10 (2.50) a.1. Engine Overspeed (1035 RPM)

2. Low jacket water pressure (10 psig) if Engine speed > 200 RPM and the Governor Shutdown Solenoid is not energized.

3. Unit Start Failure

4. Low lobe oil pressure (17 psig) if Engine speed > 200 RPM and the Governor Shutdown Solenoid is not energized.

(0.5 each) (2.0)

b. True (0.5)

REFERENCE KEWAUNEE SD No. 10 p.18,42,43 and Alarm Response Sheet 47029-31 ANSWER '2.11 (1.50)

a. Containment spray is automatically activated by a hi-hi containment pressure signal.(0.25) If one of two pressure detectors (0.25) sense a containment pressure of 22.7 +/- 1 psig (0.25) a bistable is activated.

When three out of three bistable devices activate (0.25) a hi-hi containment pressure signal results.(0.25) (1.25)

b. Smoke or air is injected into the header.

(0.25) REFERENCE KEWAUNEE SD No. 23 p.5,10 and DWG E1604; E1609 ANSWER 2.12 (1.00) An ELECTRICAL interlock (0.25) will trip the Main Turbine (0.25) when a Main Steam Isolation Valve disk (0.25) moves from the full open position. (1.0) REFERENCE 4 KEWAUNEE SD No. 6 p.4

• 2.' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 26 ANSWERS -- KEWAUNEE

-87/02/17-VICTOR,F. ANSWER 2.13 (1.50)

a. Air accumulators (0.5) are installed to operate the relief valves.(0.5)

(1.0)

b. To relieve the combined capacity of the pressurizer safety valves.

(0.5) REFERENCE KEWAUNEE SD No. 36 p.8,9 and Operating Procedure E-AS-01 p.3 ANSWER 2.14 (1.50)

a. Normal--Demineralized Water Header Emergency--Service Water System (0.25 each)

(0.5)

b. Bus 1-51 (480V) for pump 1A; bus 1-61 (480V) for pump 1B (0.5 ea.)

(1.0) REFERFNCE KEWAUNEE SD No. 31 p.2,7 and DWG E240 t I l t e .~. ,----,..,.-.e,-

' 3.' INSTRUMENTS AND CONTROLS PAGE 27 ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. ANSWER 3.01 (2.50) a.1. The condensate header bypass valves will open.(0.25)

2. After 2 minutes (0.25) (if the pressure has not recovered) the Feedwater Pump will trip.(0.25)

(0.75) b.1. Need one Condensate Pump running for each Feedwater Pump.

2. Must have seal water flow (5gpm).

3. Need lube oil pressure (8psig).

4. Need sufficient feedwater pump suction pressure (200psig).

(0.25 for each) (1.0)

c. Discharp isolation valve closes;(0.25) recirc line control valve closes;(0.25) as a result of a FW pump breaker opening.(0.25)

(0.75) REFERENCE KEWAUNEE SD No. 5A,p.8,10; DWG E1624-E; OPERATOR TM p. V-2.5 i ANSWER 3.02 (2.00) a.1. All step counters on the control board.

2. Master cycler reversible counter.

3. All slave cycler counters.

4. Bank overlap counter.

5. All internal memory and alarm circuits.

6. All P/A converters in the RPI system.

(any 5 at 0.3 each) (1.5)

b. Automatic rod control is inhibited.(0.1) Rods can be moved manually (0.2) but only by individual control banks.(0.2)

(Except for the bank with the failure.) (0.5) REFERENCE KEWAUNEE OPERATOR TM p.IV-3.15 ANSWER 3.03 (1.50)

a. True

b. False

c. False (0.5 each)

(1.5) REFERENCE KEWAUNEE OPERATOR TM p.IV-1.10,IV-1.11,IV-1.36

3.' INSTRUMENTS AND CONTROLS PAGE 28 ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. ANSWER 3.04. (1.75)

1. Source range' high flux

2. RCP undervoltage

3. RCP underfrequency

4. Pressurizer low pressure

5. Pressurizer high level

6. Loop low flow

7. Turbine trip (0.25 each)

(1.75) REFERENCE KEWAUNEE OPERATOR TM P.IV-11.10, IV-4.1 ANSWER 3.05 (2.00)

1. Modulates three way letdown valve (0.3) at 56%(0.2)

2. Full divert to hold-up tank (0.3) at 78%(0.2)

3. Resets three way letdown valve (0.3) at 70%(0.2)

4. Automatic makeup control (0.3) ON at 17%(0.1) 0FF at 28%(0.1)

5. Emergency makeup from RWST(0.3) at 5%(0.2)

(2.00) (Any four) REFERENCE KEWAUNEE SD No. 35 p.22 ANSWER 3.06 (2.50)

1. 1/2(0.25) IR greater than(35% +/-1%) power.(0.25)

2. 1/4(0.25) PR greater than (103%) power.(0.25) 3-2/4(0.25) OP delta T (5%) less than trip point.(0.25)

4. 2/4(0.25) OT delta T (5%) less than trip point.(0.25)

5. 1/1(0.25) Impulse pressure less than (15%) power.(0.25)

6. Bar.L D Rod Withdrawal Limit,(0.25) 220 steps.(0.25)

7. Urgent failure.(0.5)

(2.5) REFERENCE KEWAUNEE OPERATOR TM p.IV-12.21, V-2.3 and IV-1.18 ,m-

' 3. INSTRUMENTS AND CONTROLS PAGE 29 ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. ANSWER 3.07 (1.00) The steamflow-feedwater flow mismatch signal is sensed immediately(0.25) while the level signal is delayed.(0.25) The initial change in feedwater flow reduces the effect of " shrink" or "swe11"(0.25) by the time the level controller takes affect.(0.25) (Similar wording acceptable) (1.0) REFERENCE KEWAUNEE OPERATOR TM p.IV-10.5 ANSWER 3.08 (2.50) a.1. Both spray valves open.

2. All Pressurizer heaters turn off.

(0.75 each) (1.5)

b. The reactor trips (on OT delta-T).

(1.0) REFERENCE KEWAUNEE OPERATOR TM p.IV-8.6 to IV-8.15; IV-11.6 ANSWER 3.09 (2.00) a.1. SI Signal

2. UV on 4160 volt safeguard bus.

3. Turbine Trip.

(0.5 each) (1.5)

b. Two additional or a total of three attempts.

(0.5) REFERENCE KEWAUNEE SD No.10 p. 24,40

=. - 3' INSTRUENTS AND CONTROLS PAGE 30 ANSWERS -- KEWAUNEE -87/02/17-VICTOR,F. ANSWER 3.10 (3.00)

a. IN(0.25)---Loop B Tcold increases to Thot causing loop B Tave to increase above Tref.(0.5)

(0.75)

b. IN((0.25)---Loop A Tave will become the auctioneered high Tave which is sensed to be higher than Tref.(0.5)

(0.75)

c. NO MOTION (0.25)---Loop B Tave will decrease and will not affect the auctioneering circuit.(0.5)

(0.75)

d. IN(0.25)---Power mist.atch circuit senses a power rate change with turbine power decreasing faster than nuclear power.(0.5)

(0.75) REFERENCE KEWAUNEE OPERATOR TM p.IV-3.4, IV-3.5 ANSWER 3.11 (1.50) a.1. Condenser vacuum > 24psig +/- 2psig.(0.5)

2. At least one Circulating water pump must be running.(0.5)

(1.0)

b. Tave (0.5)

REFERENCE KEWAUNEE OPERATOR TM P.IV-9.4 to IV-9.9 ANSWER 3.12 (1.50)

1. Safety injection signal l

2. Blackout (sequencer step 9) signal

3. High radiation level on R-23

4. Steam exclusion zone SV area signal (any three at 0.5 each)

(1.5) l REFERENCE KEWAUNEE SD No. 25 p.13

5 ' 3 '. INSTRUMENTS %ND CONTROLS PAGE 31 ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. ANSWER 3.13 (1.25)

1. Trips the breakers feeding the 4160 V buses from the Main Auxiliary Transformer.

2. Trips generator excitation circuit.

3. Trips main Turbine.

4. Initiates voltage restoration to buses 1-1,1-2,1-3 and 1-4.

5. Starts the Emergency Diesel Geneiator

6. Trips substation lockout relays (86/MTB1A and 86/MTB1B).

(any five at 0.25 each) (1.25) REFERENCE KEWAUNEE SD No. 43 p.28,29 and 44 l

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 32 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. ANSWER 4.01 (2.00)

a. E-0, Reactor Trip or SI (.25) and FR-S.1, Response to Nuclear Power Generation (.25)

(0.5)

b. Open the supply breakers (0.5) for Bus 1-33 and 1-43(0.5) to deenergize the Rod Drive MG sets.(0.5)

(1.5) REFERENCE KEWAUNEE Operating Procedures E-0 AND FR-S.1 ANSWER 4.02 (1.50)

a. Blocked air dryers (0.25) and the dryer bypass valve has not opened.(0.25)

(0.5)

b. 60 psig.(0.5) Pneumatic controls for reactor and safeguards systems are not reliable below this pressure.(0.5)

(1.0) REFERENCE KEWAUNEE Operating Procedure A-AS-01 p.2; E-AS-01 p.1; N-AS-01 p.1 ANSWER 4.03 (1.50) e

a. False

~

b. False

c. True (0.5 each)

(1.5) REFERENCE KEWAUNEE Operating Procedure A-MI-87 p.1; A-MI-87B p.2;E-FP-08 p.3 l l

• 4'.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33 RADIOLOGICAL CONTROL ANSWERS - REW4llNFF o t 'na 1 ~ m v : ANSWER 4.04 (2.50)

a. 1. The RCS has been borated to the cold shutdown boron concentration.(0.5)

2. The RCS has been corated to at least the hot shutdown boron concentration and the RCS is being maintained greater than or equal to 540 degrees F.(0.5)

(1.0) b. To prevent inadvertent Safety Injection.(0.5) When pressurizer pressure exceeds 2000 psig.(0.25) Safety Injection is automatically unblocked.(0.25) If either(0.25) Steam Generator is at or below 500 psig Safety Injection is initiated.(0.25) (1.5) REFERENCE KEWAUNEE Operating Procedure N-CRD-49B; p.1; N-0-01 p.7; Operator TM p.IV-11.13 t ANSWER 4.05 (2.50) a.1. S.G.1A[comon blowdown valvh. shut.

2. Sample valves for S.G.1Afff

3. ". cute condenser air ejector discharge to Auxiliary Building exhaust.

(0.5 each) (1.5)

b. Surge tank vent valve shuts.

(0.5)

c. No action (alarm only)

(0.5) REFERENCE KEWAUNEE Operating Procedure A-RM-45; SD No. 45 p.9,10,12 i

4

I. PROCEDURE

S - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. ANSWER 4.06 (2.50) 1. Verify reactor trip. a. Trip and bypass breakers open. b. Neutron flux decreasing. 2. Verify turbine trip. a. All turbine stop valves closed. 3. Check RCS isolated. a. Pressurizer PORVs closed. b. Letdown isolation valves closed. c. Excess letdown isolation valves closed. 4. Verify AFW flow >200 ppm. (10 at 0.25 ea) (2.5) REFERENCE KEWAUNEE Operating Procedure ECA-0.0 p.3 ANSWER 4.07 (2.00) At least one (0.5) Safety Injection pump running (0.5) and RCS pressure (0.5) less than 1240 psig.(0.5) [1400 psig for adverse containment] REFERENCE KEWAUNEE Operating Procedure E-1 p.3 l O I J i

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 35 l RADIDLOGICAL CONTROL ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. l AASWER 4.08 (1.50) Grcup answers into these categories: 1. All operations affecting the operation of the reactor or major unit equipment. 2. Changes in reactor coolant boroa concentration. 3. Changes in reactor power level and Denerator output. 4. Performance of unit surveillance testing or special testing. 5. Instrumentation or equipment failures. 6. Occurrence of significant annunciator alarms. 7. Time generator placed on or taken off. 8. Changes in plant electrical lineup. (other answers will be evaluated on a case basis) (Any five (5) answers at 0.3 each) (1.5) REFERENCE KEWAUNEE Administrative Control Directive No. ACD 4.8 l ANSWER 4.09 (2.50)

a. 1. Steam Generator 1A

2. Steam Generator IB

3. Residual Heat Removal Train A

4. Residual Heat Removal Train B (any 2 at 0.5 each)

(1.0)

b. Restore the PORY to operable condition within one hour (0.5) or close the associated block valve (0.5) and maintain the block valve closed by adminstrative procedures.(0.5)

(1.5) REFERENCE KEWAUNEE TS 3.1-la; TS 3.1-2a ANSWER 4.10 (1.50)

1. Nuclear Instrumentation

2. Flux tilt indication.

3. Rod motion since last known rod position l

4. Any reactivity insertions observed

5. Single or multiple misalignment

6. Characteristic (fluctuating indicators) of misaligneo indication

7. Core exit thermocouple indication (any 3 at 0.5 each)

(1.5) l l

' 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 36 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE -87/02/17-VICTOR, F. l REFERENCE KEWAUNEE Standing Night Order dated July 27,1984, "IRPI Technical Specificattori Interpretation" ANSWER 4.11 (2.50) Pit sump valves will automatically close on high level in the sump. (0.5) Operator Actions: --Verify automatic action has occurred --Stop RHR pumps --Close RhR Return Isolation Valve (RHR-11) --Close RHR Inlet Isolation Valves (RHR-1A,B and 2A,B) --Close RHR to Letdown Line (LD-60) --Close RHR Cross Ccenection to CVCS (RHR-210 or 211) (Any 4 of the above operator actions at 0.5 each) (2.0) -- j (shMisb aHernat decy heal removal Edh h shw. gewrator or'iiike REkEkNCE SNP N'6 KEWAUNEE Operating Procedure A-RHR-34 p.2 ANSWER 4.12 (1.50)

1. Increase in audible count rate.

2. Increase counts on Source Range NI.

3. Indication of malfunction of Reactor Makeup Water System.

4. High Flux at Shutdown Alarm.

5. Reactor Trip on Source Range High Flux.

(any 3 at 0.5 each) (1.5) REFERENCE KEWAUNEE Operating Procedure A-RC-36F, p.1 ANSWER 4.13 (1.00) a.1. Originating Department Supervisor

2. Radiation Protection Supervisor or Designated Alternate

3. Shift Supervisor (0.25 each)

(0.75)

b. Unexpected, or excessivo, or if it exceeds 3/4 scale (any one for full credit)

(0.25) l REFERENCE KEWAUNEE Rad Protection TM p.II-1, IV-2 (Plant Specific Section)

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