ML20127G598
| ML20127G598 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/02/1985 |
| From: | Brockman K, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127G540 | List: |
| References | |
| 50-321-OL-85-01, 50-321-OL-85-1, NUDOCS 8505210098 | |
| Download: ML20127G598 (267) | |
Text
{{#Wiki_filter:. ENCLOSURE 1 EXAMINATION REPORT 321/0L-85-01 Facility License: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Facility Name: E. I. Hatch Facility Docket Nos.: 50-321 and 50-366 Replacement and Requalification examinations were administered at Edwin I. Hatch Nuclear Plant near Baxley, Georgia.
/ o Chief Examiner: N. l . ')kman,-
;e+ -m ~ v/2 /FT Ken E. Br Date Signed Approved by: DAAc.1 e fs~
Br,wte A. Wilson, Section Chief Ddte Signed
SUMMARY
Replacement examinations on March 11-14, 1985 Requalification examinations on March 11-14, 1985 Written, ' oral, and simulator replacement examinations were administered, as required, to three SR0s and one R0; all candidates passed these examinations. Written and operating requalification examinations were administered to seven SR0s (six written exams /six simulator exams /seven oral exams) and five R0s (four written exams /three simulator exams /five oral exams); four of the SR0s and all five of the R0s passed these exams. (Two of the SR0 failures were one-section written failures only.) The performance on the recualification examinations-(75% pass rate) has resulted in a determination that Plant Hatch's accelerated requalification training program is proceeding satisfactorily, as of March 1985. Final determination as to its success will be made after the July 1985 results are evaluated. O l 6 05 h21 PDR
u-- REPORT DETAILS
- 1. Facility Employees Contacted:
J. Badgett, Manager-Nuclear Training Corporate (E) P. Bennett, General Physics Instructor (E) K. Elliott, General Electric Instructor (R) D. Giddens, Simulator Instructor (R) L.-Gooden,. Simulator Instructor (R/E) R. S. Grantham, Supervisor-Operations Training (R/E) T. Greene, Deputy General Manager, Hatch (E) J. Lewis,-Operation Department, Hatch (E)
. M. Marlow, General ' Electric Instructor (R/E)
D. Matherly, General Physics Instructor (R) B. Moll, General Electric Certification Engineer (R) C. T. Moore, Training Manager, Hatch (E) G. Neeley, Simulator Instructor
'H. Nix, General Manager, Hatch (E)
R. Rutan, General Physics Instructor (R)
- B. Smith, Simulator Instructor (R) '
L. Sumner, Op'erations Manager, Hatch (E) NOTE: "R" indicates present at examination review "E" indicates present at exit meeting
- 2. NRC Personnel
.a. Examiners K. E. Brockman, NRC S. Guenther, NRC W. Hehl, NRC J. Munro, NRC G. Sly, PNL L. Wiens, NRC
- b. Resident Inspector
-P. Holmes-Ray, Senior Resident Inspector, Hatch
- 3. Examination Review Meeting At the ' conclusion of the written examinations, the examiners met with facility representatives to review the written examination and answer key.
The following comments were made by the facility reviewers: - C
s 2
- a. SRO Exam (Replacement)
(1) Question 5.08
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Facility Comments: Response "b" (supposed correct answer) shows' a Xenon . free condition from 100%' power in 35 hours. L-RQ-606 (A.1.g.) indicates Xenon free conditions require 72 hours. Question should be deleted. NRC Resolution: Response "d" shows the Xenon decay over a 72-hour period. This will be accepted as an alternative response to the question. (2) Question 5.10
. Facility Comments:
(a) It is difficult to determine which part of the curve is being referenced. Recirculation Pump Runback should be accepted as an alternative response. (b) Answer key indicates that the pressure increase is due to MSIV closure; integration of ATTS now has MSIV closure at
-121" with HPCI initiation at -55" (38" UI). Alternative response should be "CV closure" or "CV closure w/BPV F.S."
(c) Answer key indicates pressure fluctuation due to SRV cycling. With LLS in effect at Hatch, the cause of this should be HPCI (RCIC) cooldown effects. NRC Resolution: (a) Graph is specific as to point in question. -No changes to - answer key made. (b) ATTS integration allows for new cause of pressure increase. Review of graphs shows pressure increase to greatly exceed 920# Pressure Set for EHC, however; thus, only the alternative response of "CV closure w/BPV F.S." is accepted. (c) Answer key changed to reflect correct response. (3) Question 5.13 < Facility Comments: e Attached graphs do not allow the calculation of any of the - responses provided. Delete question since there is no correct answer. L
r 3 NRC Resolution:
-Question deleted. Discrepancies between current and previous MCPR gr aphs caused f or incccurate refere .ce material being provideo to examinees.
(4) Question 5.17 Facility Comments: If the circ water flow increase required to increase vacuum significantly increases condensate depression, efficiency goes dawn. Delete since answer could be TRUE or FALSE. NRC Resolution: Answer unchanged. - The conditions did not - tell the candidate to assume a significant condensate depression increase. Also, the change in condensate depression would need to be very excessive to establist. an efficiency decrease. (5) Qus tion 6.03 Facility Comments: This question requires an in-depth knowledge of the diesel generator synch acceptor circuit. This circuit is not addressed in the GPC traintag manual, nor could an operator determine how it operated from looking at the elementaries (it is black-boxed). No where in the training curriculum is an instructor required to cover the operation of the synch acceptor circuit, and often times it was not covered because the elementaries have never ~been received which cover its operation; therefore, its operation has never been fully verified. There have been numerous problems on the simulator concerning D/G logics and D/G output breaker logics during the requal training period which has, understandably, raised questions as to the simulators response to various posed scenarios. Therefore, the requal and initial license personnel could 'not use it (the simulator) as a sole source for answering D/G logic questions. In light of the above stated facts, any NRC question as to how the synch acceptor circuit functions should be removed from the exam. , NRC Resolution: 1 It is agreed that an understanding of the impact that the synch l acceptor circuit has on D/G operations is required. However, 4 detailed electrical knowledge (inside the black boxes) is not being queried. This has been a previously identified shortcoming . in candidate performance on simulator exams and resulted in a i
7: 4 design change to the simulator in late 1984. Since there are two
. procedures.to manually tie the D/G to a bus, it is essential that the operator know the operational restrictions that the different ni ct. s of D/G eperation impose. Initial review by the f acility verifies the technical accuracy of the question. No change to the answer key will be made.
(6) Question 6.13 Facility Comments: Response "d" is also correct as per GPNT, Vol. V, Chapter 2.3-14. NRC Resolution: Response "d" included as an alternate answer. (7) Question 6.21 Facility Comments: This question is unfair to the operator because there is no way an operator could withdraw rods into this configuration without violating both procedures and TSs. (a) RSCS would have to have been bypassed - TS and HNP-2(1)-9207 specifically disallow this. (b) HNP-2(1)-9207 rod withdrawal pull sequence would have to be violated to achieve this rod pattern (i.e., rod 34-27 can not be withdrawn past position 04 in Group 4). Therefore, this is a very unrealistic and hard to understand question which requires the operator to regurgitate the RWM program and apply it to a situation any safe operator could never be in without violating several procedures and deliberately bypassing a system (RSCS) specifically required to be operable for continued plant operation. The question should be deleted. NRC Resolution: While it may be difficult for an operator to get into the operational configuration posed by the question, it is a straight forward and unconfusing scenario. Not addressing the potential for violating rod movement procedures, the question asks the operator for the control room indications he would expect for o given rod patterns. It requires application of the RWM 1pgic, not l regurgitation, and is directly oriented to the operating e environment. No changes to the question or answer key will be made. . o
5 (8) Question 8.09 Facility Comments: Response "d" is a FALSE statement, per-HNP-504 B.6. NRC Resolution: Comment not allowed. The purpose of HNP-504 is to, "... provide a method to control all temporary jumpers and lifted wires... where an approved plant procedure is not available. . ." Response "d" addresses the use of temporary jumpers during surveillance proce-dures and is, therefore, covered by HNP-9.M.a.(1), which supports a-TRUE response. (9) Question 8.15 Facility Comments: The Unit 2 Tech Specs state that Operational Condition 5 is when the RPV head volts are unbolted or the head removed. Detensioned-doe's not mean unbolted. Operational Condition 4, Cold Shutdown should be accepted as an alternative response. NRC Resolution: Comment not accepted. Detensioning of the head bolts establishes the initiating of unbolting and effects the establishment of Operational Condition 5. This was confirmed with the Senior Resident Inspector for the site.
- b. SR0 Exam (Requalification)
No new items were identified by the utility. Subsequent review by the NRC identified response "c" as an alternative response. to Question 8.07.
- c. R0 Exam (Requalification)
No new items were identified by the utility. Subsequent review by the NRC identified unconsistencies in the construction of Question 3.01; the distractors were not focused to the point of being unconfusing. The question was deleted. O e { s
V. .
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- 4. Exit Meeting
._At-the conclusion of the site visit, the examiners met with representatives of ~ the ' plant . stc ri _ to discuss ttic results of the e x ami r.at i a. . i r,c se
' individuals who clearly passed the operational examination were identified.
There were _no' generic weaknesses (greater than 75 percent of candidates giving incorrect answers to one examination topic) noted during the oral examination. Two items of . interest were shared with the plant management for their-review:
- a. Procedure HNP-3801 had a Pen and Ink Change (#35) issued on
-December 18, 1984. Instructions on- the procedure indicated that a typed copy was to follow. . As of 3/14/85, the pen and ink change was still in_ use; this provided an opportunity for misinterpretation' and misapplication by the operating staff. (SRI will follow up.)
- b. The need for an instrument cross-reference between instrument numbers, surveillance procedures, 'and Tech Spec requirements was noted. (This comment was given as a suggestion for improvement and does not require followup tracking.)
The cooperation given to the examiners and efforts to ensure an atmosphere in the ' control room conducive to oral examinations was also noted and appreciated.
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i kh3M i temi c' E(\ El oso ce_ 3 U. S. NUCLEAR, REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: HATCH 1&2 REACTOR TYPE: BWR-GE4 DATE ADMINISTERED: 85/03/11 EXAMINER: K E BROCKMAN APPL'ICANT: ________________________, INSTRUCTIONS TO APPLICANT: 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 f e rs t 80%. Enamination papers willfbe picked up six (6) hours after the examinatiori starts.
< *: OF CATEGORY % ' 0F. APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
_"III_3 0_ ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS, AND 19.0c THERn0 DYNAMICS 30.00 'S ________ 4 PLANT SYSTEMS DESIGN, CONTO 0L. ________ _2__.0^I AND INSTRUMENTATION 30 00 ________ 7. PROCEDUPES - NORMAL, ABNORMAL. ________ _'5 06I___I___________ EMERCENCY AND RADIOLOGICAL
. CONTROL 30 00 ~5.00 ADMINISTRATIVE PROCEDURES,
________ . ____ ___________ ________ 8. CONDITIONS. AND LIMITATIONS 42..:. 100.00 TOTALS U% .00 FINAL GRADE _________________% All work cone on this e?tamination is my own. I have neither given nor received aid.
~~~~~~~~~~~~~~
5PPL5CdhII5~5 G5ETURE
.__.._A..__
c- . p y . THEORYLOF1 NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 5. y g-------------------------------------- QUESTION 5.01 (1.00) Which of the following is NOT a characteristic of Subcritical Multiplication? ,
- a. The soberttical neutron level is directly proportional to the neutron source strength
- b. Doubling the indicated count rate by reactivity additions will reduce the margin to criticality by approximately one-half.
- c. For equal reactivity additions, it takes longer for the new equilibrium count rate to be reached, as K-eff approaches unity.
- d. If ten (10) notches.of rod withdrawal increases the SRM count rate by 10 cps,'then twenty (20) notches of rod withdrawal will increase the SRM count rate by 20 cps. ASSUME CONSTANT ROD WORTH.
QUESTION 5 02 (1.00) The change in reactivity associated with 3 chan.3a in K-eff from 0.920 to 1.004 is approx 2mately ... (CHOOSE ONE)
- s. 0.001
- b. 0.084-
- e. 0.087
- d. 0 080 GHESTION 5.01 (1.00)
A ' Periodic NSSS Core Performance Log' P-L) is attached for reference. Which statement is most accurately reflected bv this printout?
- 3. Maximum LHCP(s) in the core is 12.00 Kw/ft.
- b. M s:timum L HGP ( s i in the core is ~.64 Kw/ft.
- c. ti a ::i m u m LHCR(s) in the core is 11.40 Kw/ft.
- d. Manimum LHGRIs) in the core is 9.10 Kw/ft 1- - - - _ _ . _ _ _ _ - _ - . . . _ ,
U.l.
- ?
THEORY OF-NUCLEAR POWER PLANT GPERATION, FLUIDS, AND PAGE 3 5; gg g-------------------------------------- I' GUESTION. 5 04- (1.00) The condensate _subcooling in a' condenser operating at 1 PSIA, with a condensate temperature of 95 deg F is ...-(CHOOSE ONE)
- a. 6.7 des F
- b. 196.7-deg F c.. 10 7 deg F
- d. 120'.'3 des F QUESTION 5 05- (2 001
'The' attached figure shows a basic closed loop fluid system with
~its head vs. flow Plot _(BOLD LINES). The two pumps are identical, "artsbie speed. r3disi, centrifugal pumps. Pump i is initially-operating at one-half speed to supply flow to component 1, as shown.
- a. Component 2 is placed into service. thereby increasing the-system hest lose). Would total pcwer consumption be less by ...(CHOOSE ONE)
(1) Doubling the speed of Pump 1 (21 Starting Pump 2 at one-half speed- (0.5)
- b. uhtch Pump Curve - A. P. C, or 0 - most accurately shows BOTH (0.5)
PUMP 3 oper = t treg to supply the system flow?
- c. W ith ontv Fump 1 opersting >3 t one-half speed - If component 2 were throttled open from its initial position. would the system flou INC6 EASE. OECREASE, or OEMAIN THE SAME? (COMPONENTS 1 & 2 (0.55 APE IDENTICAL'1
- d. Given one opersting comp, that is chanjed to i POSITI'/E DISPLACEMENT Is the correct Pump Curve to reflect this Curve A. B, C. or D? (o.5r pumo.
{f- . 4 ] l l THEORYLOF~ NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE 4 i5. GUESTION :5.06 ( 1 50) MATCH _the appropriate Thermal Limit (3-c).
- 3. Linear Heat Generst, ton Rate (LHGR)
- b. Average-Planar Linost Heat Generation Rate (APLHGR)
- c. Minimum-Critical Power Patio (MCFR) to each" FAILURE. MECHANISM . AND to each LIMITING CONDITION given below:
' FAILURE MECHANISM ' LIMITING CONDITION F1 Clad melting cave,ed by. L1. Coolant transition decay beat & stored heat boiling following a LOCA Clad plastic ittsin-FO.- Ciad crickin3 from the surtsco L2.
becomin3 vapor "bl ank e ted' 17. - Clad'crseking caused by L '3 Maximum clad temp-F3. high stress from pellet erature of-2200 des F
. enpansion GUESTION 5 07 (1.00)
' u;1 t ch o f the following desertbes the changes to the steam that occurs between the inlet.and the outlet of a REAL turbine?
- a. Enthalpy OECREASES. Entropy OECREASES.-Quality DECPEASES
* ~.
b E n t.h s i pv INCREASES. Entropy INCREASES. Onsittv INCREASES
- c. Enthalpv C0dSTANT . Entropy DECREASES. onelitv OECREASES
- d. Entnalpy DECREASES, Entropv INCFEA3ES. ov21it. DECREASES r
r~ r - 6 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PACE 5
- 5. ------- .------------------------------
THERMODYNAMIC S GUESTION 5.08 (1.00) Given the following Power History: wo. wes so-3. (*i.) o ,
'. p c 16 .
. .. .. 3 .. oc v.mt .= tw.w.s). ... % .. ... .,, .
Select the most accurate curve displaying the expected XENON transient. 4..
= . . . ,
- a. .
[ o .. . wwn a se to v.
.. '*. s .
v .. s ( w.. . .) C. s
,. s4 . . . . . . ..6....
o s. w. .. s . v ia c ( ...a Io w = C. 6 c. .
, . , i i > > . . . , ,
S N N M %. k. .b . kb I b . kg hg %g %g T.% t ( % se r %h i k... 4.m -
- d. . . . . . . . .
* . . 'sg 'st it
$4 O e. 1. %h g. ga, . 6, 1. W f.4 8..
- 5. . tw...,s )
1 I
>A ti THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE -6 5.-
.--- g gggg gy g--------------------------------------
GUESTION 5.09 (1.00)- Which.of the following accurately describes a benefit of the Control Cell Core (CCC10 a.- The Capacity Factor is_ increased due to the elimination of i rod pattern enchanges.
- b. Operations are simplified since flux shaping is no longer required.
- c. Thermal Limit margins are increased due to the elimination of all high power fuel bundles.
- d. Fuel reliability has been improved due to the increased PCIONR ramping rates which have been incorporated.
QUESTION 5 10 (2.50) The attached figure represents a transient that could occur at a BWR. Given: (1) All FW Pumps trip at time T=1.2 min (2) No op_er8 tor 3Chions occur (3) Recor der Speed = 1 division = 1 minute EXPLAIN the c30se(4) of the following recorder todications
- a. Core Flow DECREASE (Point A)
- b. Peacter Pressure INCREASE
- Point B)
- c. Level INCREASE (Point Cs
- d. Pressure FLUCTUATION (Point D G Time 3 - 7 minutes)
- e. Reactor Power DECREASE (Point E)
OVESTION 5.11 (2.50) The attached figure represents a trinstent that could occur at a SWR. Given: (1) E.oth Recireviation Pumps tric et time T = 1 min (2) No operitor actions occur (3) Recorder Speed = 1 division := 1 minute EXFLAIN r.he cause(s) of the following recorder indications:
- a. . Core Flow DECREASE (Point A)
- b. Lev 91 INCREASE (Point 86
- c. FW Flow DECREASE ' Point CS
- d. Power INCREASE (2.2 - 3.2 mtnotes - Fotnt 0)
- e. Whv did forbine Steam Flow stabilize at approntmately 50%S
___--___________________,_1_____ __
m.
.g.
s- . THEORY 0F NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7 5.. ggg7gggggg-------------------------------------- QUESTION 5.12 (1.00)
-A reactor heat balance was performed (by hand) during the 00-08 chift due to the Process Computer being 00C. The GAF's were computed, but the APRM GAIN ADJUSTMENTS HAVE NOT BEEN MADE.
.Which of the following statements is TRUE concerning reactor power?
- a. If the feedwater ~ temperature used in the heat balance esicu-lation'was LOWER than the actual feedwater temperature. then the actual power is HIGHER than the currently calculated power.
- b. If the reactor. recirculation pump heat input used in the heat balance esiculation was OMITTED, then the actual power is LOWER than the currently calculated power.
- c. If the steam flow used in the heat balance calculation was LOWER than the actual stasm flow. the.: the actual power is LOWER than the corrently calculated power.
- d. If the RWCU return temperature used in the heat balance cal-colation was HIGHEF than the ac tual RWCU return temper store, than the actual power in LOWER then the currently calculsted power. .
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r 1: 4 THEORY OF NUCLEAR POWER PLANT OPERATION,' FLUIDS, AND PAGE a
.5.
g-------------------------------------- s --_-----_----- t .co QUESTION 5 13 (W Given: Reactor Power 60% Core Flow 40% T (Tau) .6 Fuel-Type R8x8R Max Flow Rate 107% Figures 5.4, 5.5, 5 6 Enclosed 0"000: 07' (1 0)
- . O '_ " C * * .: .
(1) 1.731 (2) 1.._ Dc.(=.1.=k 1 5'39 s : 1. G ; I
- b. If the r1CPR Printout from the Process ComPoter for Rod ?-17 read 1 973, which of the fo110 win 3 would be required per Unit 2 Tech Specs?
(1) No Action Required l^1. Cottiate corrective iction within 15 mtnotes ind continue the corrective action so that HCPR is within the applicable limit , atthin hours. or reduce thermal power to ' 25% within the neut 4 hours. I '3 \ Initiate correctiv ? sction within 15 minutes and continue the corrective action so that MCPP is within the applicable limit within 4 hours, or reduco thermal power to 25% within the n e .: t 9 hours. t4' Pince the reactor in HOT SHUTDOWN stthtn ; hours snd reduce steam dome grassure to s 785 ps13 ind core flow to 10% withtn 'he nent J hcurs. GHESTION 5.la r1.00s the fission ,orocess in a commercial reactor requires the nautrons that are ' born' bv fission to be 'thermalized.' The interaction in tha reactor core which ts most efficient. in ther m e !i .tn 3 neutr oni
'for fission occori with the ...(CH00GE ONES
<. G O CEt1 e t.o m s in t he w 2 tor mo19evles
- b. BORON etomb in the control rods
- c. .: CPCONIllH a toms in the rual claddin3
- d. HYDROGEN 4 toms in the witer moleevle,
. t.
9' : THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE ? 5.-
--- y gg ggg--------------------------------------
'4UESTION 5 15 'I .50)
' Answer.the following TRUE or FALSE:
With a reactor that is critical. low in the intermediate range, an EQUAL amount of POSITIVE or NEGATIVE reactivity insertion (e.g. 10E-4 k/ki atll produce stable periods or EQUAL MAGNITUDE. QUESTION 5 16 (2.00)
-STATE how fuel pin centerline temperatu'e will change (INCREASER DECREASE, or REMAIN THE 3AME) with each of the following conditions.
- a. A 0 001 inch thick layer of corrosion product deposits on (0.5) the clad-surface.
b.- The Pressure set on EHC os lowered by 10 psig. (0.5)' ( 0. 5 ).
- c. A fuel bundle reaches DNB.
(0,5)
- d. A HPCI-full flow surveillince is conducted.
s l
C-THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 10 5.
--- g ; gggg--------------------------------------
GUESTION 5.17 (1.00) The BWR is designed to operate like e. h e PANKINE VAPOR CYCLE, shown below. Select the s t a t e m e ri t wh10h is NOT TRUE. as applies to the REAL BWR cycle. C Is Temperature B
- E A
Entropw
- a. Increasing condenser vacuum ( 25' changao to 29') INCREASES cycle efficiency.
- b. Condensate Depression, which is reovired for proper plant equip-ment performance, INCREASES overall thermodynamic afficiency.
.: . Feedwater Heating INCREASES overall thermodynamic efficiency.
- d. Feedwater pump pressure increase causes the feedwater to be FUPTHER from saturation conditions.
8
y j~. AND PAGE 11
'5.: THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,------
gggggggg------------------------------- QUESTION 5 18 (2.00)
'Ccncerning General Electric's Preconditioning Interim Operating Mcnagement Recommendations (PCIOMR):
- a. Starting with the fuel at a threshold of 11.0 kw/ft. a maximum
'ra:p increase is begun at time 0000 and the final desired power of At this time, the required soak is 13 0 kw/ft is achiesed at 2000.
-porformed.FOR.10 MIPUTES, at which time the load dispatcher directs a power reduction. that tak es nodal power down to 12.0 kw/ft. SELECT tho valid preconditioned.value t'or this node.
ASSUME THE MAXIMUM RAMP RATE IS .10 Kw/ft/hr
\\ 11.0 ku/ft
.2) 11 8 kw/ft
?) 12.5 kw/f',
- 4) 13 0 kw/ft
- b. '9 ELECT the' minimum time which wovid be reqvtred to raise power back to 13 0 >w/ft. given the above maximum camp rete.
15 Immediate (Raise to 13.0 kw/ft, w/o restrtctions) 21 5 hours
- 9) 12 hours
- 4) 20 hours GUESTION 5.10 (2.00)
As part of the scram procedure, the operator is directed to insert the SRM's and IRM's.
- a. Following a severe LOCA, EXPLAIN how these systems could be (1.0) used.to detect gross core damage.
- b. EYPLAIN how these systems could be used to provide e crude indicstion of water level if level could not be confirmed by (1.0) normal instrumentation.
C..'. v THEORY OF N,0 CLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 12 5. q g-------------------------------------- OllESTION 5.20 (1 00) Which of the following statements best describes the operating characteristics of an LPRM detector? i
- o. Depletion of the detector's uranium coating causes both the neutron and the samma sensitivity to DECREASE with detector aset the resviting neutron to samma signal ratio remains relatively CONSTANT.
b, since the detector fonctions as an iont:ation chamber and the Argon gas pressure remains relatively CONSTANT, BOTH the neutron and the gamma sensitivity, as well as the neutron to samma signal ratto, remain relatively CONSTANT as the detector ages.
- c. Depletion of the detector's uranium coating causes neutron sensitivity and the neutron to gamma signal ratto to DECREASE 4tenificantly as the detector ages
- this may impair the detector's
-ability to respond to changet in power.
- d. Depletion of the detector's oranium coating causes a OECREASE in the neutron to gamma signel ratio as the detector ages, but this coes not impatr the detector's responte since gamma discrtmination is not required in the power range.
OllESTION 5 21 (2.00)
- s. After a reactor Scram from power, the shortest STABLE period (1.0) possible is - 80 seconds. EXPLAIN why.
Li . Is the INITIAL oeriod IMMEDIATELY rollowing the above described Scram SHORTEP or LONGEP than the 30 seconds. (1.0* E(PLAIN.
F~ 61 PLANT SYSTEMS DESIGN, CONTROL, AND. INSTRUMENTATION PAGE 13 OUESTION 6.01 (1.00) The Drywell Pneumatics System is operating in its normal line-up
~
(hode B). Pressure DECREASES (to approximately: 100 psigi. The Ervstem will.sutomatically .siign such that ...(CHOOSE ONE) 8 -...the back-up Nitrogen supp1v line. isolation valve (F001A) will OPEN.snd the bypass valve (F0018) will CLOSE.
- b. ...the back.-up Nitrogen supp1v line isolstion valve (F001Ai will GPEN and the bypass valve I F O O 1 B ', will.0 PEN.
c .- ...the Essential /Uninterruptable Instrument Air supply line isolation valves (F029 & F053) will 0 PEN.
'd. ...the Non-essential /Interruptaole Instrument Air supply line isolstion valves (F034 i F038) will GPEN and the Drywell Pneumatics Compressors will TRIF and ISOLATE.
GUECTION 6 02 (1.00) Given s-Low CST Levet on Unit 1 AND 3 High Torus Level on Unit 2. uhich one of the following accuratelv describes the responses of the HPCE and RCIC Systems?
- a. BOTH units' HPCI AND RCIC will soto-swao to Torus Suction.
- b. Unit : HPCI AND FCIC will sutc-swap to Toros ?vetioni Unit 1 will auto-swas for HPCI ONLi.
.. Unit 1 HPCE AND FCIC will auto-swap to Toros luctioni Unit 2 will auto-swas for HFCI ONLY. inctioni FCIC does not' swap.
4 80TH untts' 'dPCI will auto-swap to T o r o 's 9 m
{ f. t c6a -~ PLANT SYSTEMS DESIGN, CONTROL, .AND INSTRUMENTATION PAGE 14 QUESTION 6 03 (1.00) Given: Unit 2 in control of D/G *B' (Surveillance being performed) D/G *B' Mode Switch'in TEST Electrical. distribution NORMAL (Full Power Lineup) D/G.'9' is at-rated speed and voltage, but not synchronized. when power is lost-to 4140 volt Bus 2F. Which of the followins securately describes the system operation?
.0, Bus 2F can be powered by D/G 'B' when the operator takes.the Output Breaker 1 Switch to CLOSE and-has the SYNC SCOPE setivated.
- b. Bus 2F-will'be powered by D/G 'B' automatically, after 12 seconds; appropriate loads will'be picked up sequentially.
c.. Bus IF con not be powered by D/G *B' while it ts in the TEST mode, given these conditions. 6 E u4s - 2 F :an be powered by D/G 'O' when the operator resets the
-Loebout Pe13y. activates the SYNC SCOPE. and takes the Output Break er
'o 01.0GE.
DUESTION 6 0a .'1 001 The rt.2 : n Turbine ririt s tige pres tore switches provide permiss tves end or control signals for several plant fonctions. Which of the rollowing ts cl0 7 ane of 6. h e c e control ronctions?
- a. Recir cul at ion Pome- FFT breaker trip permissive
- h. PTCS bvp314
- c. D 'J M LPAP
- . T T) , it)1 Cic 1oce Scr am bypass I
_ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -s
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t PAGE 15 6.- PLANT SYSTE S DESIGN, CONTROL, AND INSTRUMENTATION QUESTION 6.05 (1.00) The Recirculation Flow 1 Control Svstem contains a 44% Speed Limiter to control Recirculation pump speed under certain plant conditions.
"This 44% Limiter ...(CHOOSE ONE)
~
- a. ...is'first_setivated when total feedwater flow decreases below 70% and a reactor vessel icw water level slarm is received.
'b. ...is designed to prevent Recirculation pump cavitation by ensurin:3. adequate Net Positive Svetion Head.
- c. ... enables the FWCS to recover reactor vessel water level upon loss of one Reactor Feedwater pump. '
- d. ... automatically resets when the initiating signal clears to enable the operator to restore normal recirculation flow.
QUESTION 6 06 (1 00 The Reactor Water Cleanup System (RWCU) ti being operated in the
' Hot Blowdown mode to control reactor water level. Which one of ,
the t'ollowin 3 limitations ts 407 a valid concern to the operator - while controlling blowdown flow rate to the main condenser? 4 Otceeding the manimum ? llowaole PGCC'J System temperature exiting the Non-Rejenerative Heat E::ch a ng e r (NPHYT.
- b. E<ceeding the ma;timum allowable RWCU system tempersture exittnj the NRHY.
- c. Exceedin3'the Pressure Setpotnt for downstream of the Blowdown FCV.
D. Exceeding the design cooling capacity of the Pegenet ative Heat Enchanger 4RHX). QUESTION 6 07 (1.00) uhtch one of the follow'ing accor1telv descetbes Low-Low 3et (LLS) logic, es applied at Plant Hstr.h? 1 Lowers BOTH the opening ind closinj setpotnti of the LLS valves.
- b. Controls the operation of all relief velves. ancepting E and H.
c I4 4ctivated by a position switen which confirma anv SPV opentng.
- d. In applicable to Unit ONLY.
PAGE 16 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUNENTATION
~
.6.-
GUESTION 4.08' (2.00)
-Pesarding the Residual Heat Removal (RHR) System while operating -
in the Shutdown Cooling-(SOC) Mode'
- a. ' STATE why it is necessary to prevent the PHR pump's discharje'from(1 0) decreasing below 400 spm.
- b. ' LIST 2 wavs in which the system will bte ef fected if reactor (1.0) pressure increases to above 135 psis.
.00ESTION 4 09 <2.00)
With regard to the Unit 2 HPCI 3vstem setpoints) which will s.- LIST the'two (2)-conditions (includir (1 0)- automatically initiate HPCI.
- b. For aach of the situations listed below, STATE whether HFCI (1 0)
WILL.or WILL NOT Automatica11v Inject into the reactor vessel. NOTE: ASiUNE NO OPERATOR ACTIONSI ASSUME ArlY FAILED-COMPONENTS WERE IN THE FAILE0 CONDITION AT THE TIME OF THE AUTO INITIATION SIGNAL. (16 The GLAND SEAL EXHAUSTEP VACUUM FUMP rat's to operate. (2' The MINIMUM FLOW UALVE fails to avto open (stavs shut) when
& stem conditions reqotre it to be open.
(3) After decreasing to 50 psig. HPCI Steam Line Pressure increases t r, 150 ;vs i g .
- 4) After increestng f.o +60 inches, Feschor Vessel Water Level decreases to -60 inches.
W M i. F I
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4 PLANT SYSTENb-0ESIGN, CONTROL, AND INSTRUMENTATION PAGE 17 4. GUESTION 6.10 (2.00) The Unit 2 Vital AC Power 120/240 v Distribution Cabinet 2A i s
-normallyLsupplied from 600 v Bus 20 through a Battery Charger znd-a Static Inverter. If the Static Inverter fails ...(CHOOSE ONE)
- a. . . . . the.125 vde batterv will maintain power to the Vital AC Cabinet for up to 6 hours,
- b. .~..the power supp1v can be minvally transfered to the alternate 600 v Bus 2C / Vital AC Transformer 2A by depressing a transfer PB.
- c. ...the power supply wt11 sutom.stically transfer to the alternate 600 v Bus 2C / Vital AC Transformer 2A.
- d. ...the power supply can be wanually transfered to the alternate 600 v Bus 2C / alternate Static Inverter by depressing a transfer PB.
GUESTION 4 11 II.00) The Unit 1 Primary Containment Atmospheric Control System can be used to vent the Primary containment under normal operating con-citions. To do this, the operstor must manipul 2te the key-locked bypass switches. The direct effect of doing this. and the method by which this is done, 1s to ...< CHOOSE ONE)
- a. ... override the HI MSL PRESSURE < 850 psig) isolation signal by HOLDING the bypass switches in the BYPASS position,
- b. ... override the HI MSL PRESSURE ( 3 S50 psig) and~the LOCA isolation sl'jnato by 40LOING the bypass swttches in the BYPASS position.
- c. ... override the HI nSL PRESSURE ( e 850 psig) isolation signals by Pl. ACING the bvpass switches in the SYPASS po'sttton.
- d. ... override the HI NSL PRESSURE ( SSO psigi and the LOCA isolation s t jn si s by PLACING the bypass switches in the BrPASS position.
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-- --_ _ - . _ _ _ L
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' 6' . : PLANT SYSTEMS DESIGN,' CONTROL, AND INSTRUMENTATION PAGE 18 QUESTION 6 12 (1.001 Unit 1 is operating--at 40*: _RTP using Reactor Feedwater Pumps 1A' cnd 18. Feedwater Line A is isolated-(HOV F006A Shut). With this condition, s flowpsth for R4CU ... (CHOOSE ONE)
- a. ...CAN BE MAINTAINED. The RuCU connection to FW Line A is isol.sted by removing the spool piece between RWCU and the HPCI discharge; RWCU is operated via RCIC and FW Line B.
- b. ...CAN BE MAINTAINED. The RWCU connection to FW Line A is isolated bv manually valving shut the connection between_RWCU and the HPCI discharge. RWCU is operated via RCIC and FW Line B.
-c. ...CANNOT BE MAINTAINED. The RWCU flow to FW Line A is not isolable since the RWCU to HPCI discharge' connection is not valved.
- d. ...CANNOT BE MAINTAINED. RWCU only has a discharge isolation valve on its common discharge Meadert no FW line can be isolated without. securing RWCU.
GUE? TION 4.13 (1.00) , Which of the following statements correctly describes the protective trip function (s) associated with the Reector Recirculation pumps / motor generator sets? 1 "he 'EOC-RPT' trip protects the plant from overpressuri:stion
. transients (e.g. MSIV Closure) by tripping the recirculation pumps. when reactor pressure e1ceeds 1120 psig,
- b. The motor generator field breaker stays closed in most instances ,
when '.he MC Set delve motor breaker trips, in order to m a>timi:e constdown flow.
- c. The two 'EOC-RPT' breakers for each recirculation pump are redundant to the MG Set drive motor breakers. and interrupt power to the MG Set during overpressuri:ation transients, d, The reactor recirev13 tion pumps trip on low low reactor ve1441 water level. to ensore Net Positive Suction Head (NPSH) requirt.ments are met. ,
; g'. ,
3 _.
- 4. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE. 19 GUESTION z4 14 (1.00) a reactor startup/ power ascent is-in progress with the 'B' IRM f ailed -upscale and in BYPASS. The mode switch has just Jbeen taken to *Run'. WHICH'one of the following situations /
events will cause e reactor HALF-SCRAM?
- n. tPRM Flow Converter (Unit).'A' goes INOP
- b. APRM.*B' #sils DOWNSCALE
- c. One of the~11 valid LPRM inputs to APRM 'B' fails DOWNSCALE
- d. .APRM 'B' Mode Swit,ch is taken to STANDBY I
u i g
8 . t ;. I CONTROL, AND INSTRUMENTATION PAGE 20
- 6. PLANT
__________' SYSTEMS DESIGN, GUESTION 6.15 (1 001 14hich of the displays of-the indicator li3 hts for ATTS indicate ! that.the system:is in its normal operatin3 mode with NO ALARM CONDITIONS present? (CHOOSE ONE) NOTE: FIGURES 9.9(3) AND 9.9(6) PROVIDED FOR REFERENCE DISPLAY / COLOR LITE / PANEL (a) (b) (c) (d) TRIP STATUS /MTU ON/ Green GUT ON/ Amber GUT STATUS /MTU' ON/ Green ON/ Green OUT On/ Red
-GROSS FAIL /MTU ON/ Green GUT ON/ Green GUT i 1
.POuER/P925 ON/ Green- ON/ Clear ON/ Red ON/ Green L
l' o
- __ - _ v
e. L r F
- PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 21 "4.
QUESTION 6 16 (2.00) ,. EXPLAIN how reactor vessel level is controlled in the dP F.ade L duringia reactor startup. Include the parameters which are sensed and the plant systems / components controlled. f GUESTION 6.17 (1.005 , I STATE how (INCREASE, DECREASE, REMAIN THE SAME) Drywell Pressure would be expected to respond to an SRV discharge line vacuum breiker-3 TICKING OPEN during actuation of the SRV. EXPLAIN YOUR
-CHOICE.
OI.tESTION 4.13 (1.00) ( u61ch of~the following is NOT TRUE regarding the operation.of the
- .1 s t n i t e i n. Isolation'Velves IMSIV'si ?
~
a.- Air pressure is normallv used to open and close the MSIV's.
- b. Ac como I a tor-s ivpply normal pneumatic pressure for valve operation- with the plant ele system providing a backup source.
- c. AC and CC solenoid talves control the admission of pneumatic pressure to each hSIV, but only ONE solenoid need be energized to r epos ;t ior. the HSIV 0F EN.
d, .Ouring test operation, the MSIV will go 20" CLOSED under spring pressure as the under-piston pressure is released through c.ne+jle valve. . OVESTION 6.10 (2 00)
-The p1snt is-operating normally at full power with the FHCS in THPEE-ELEhENT CONTFOL. A_ single SRV fails open and remains open with NO 0Feritor actions taken.
After the inittsl transient, the plant attains a new steady-state condition (the one 3RV.is still open). STATE whether the reactor water level will be HIGHER, LOWER, or the SAME is tt was before the transient. EXPLAIN voor answer. (Include control signal variances and the component responses)
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. PLANT ~ SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 22 4.
1 QUESTION 6.20 (1.00) Reactor Feed Pump (RFP) turbine speed is controlled by either
.c Motor. Speed Changer (MSC) or an Electric Automatic Positioner (EAP).. The EAP ...(CHOOSE ONE)
-a. ... . will control the RFP. turbine's speed only if tts speed signal is greater than that from the MSC.
- b. ...is normally.used to control feed flow rate .h ::t a turbine speed of 0 -- 5500 rpm.
- c. ......onlike the MSC, does.NOT afford the capability of manual epeed control by use of a local handwheel.
- d. ....will lock ~1n place to prevent 1. ramp response to a false tignal, if it loses its signal from the flow controller.
QUESTION 4.21 (3.00) Assume ~the following initial rod position distribution: All rods in Groups.1 - 3 .are FULLY uITHDRAuN, except for-one rod in each Group .---
~
22-51 in Group 1, 46-55 in Group ?? and 13-03 in Group 3 ( These 3 rods are FULLY INSERTED). All rods in Groups 4 - 10 are FULLY INSERTED to posttion 00 except for rod 34-27
- Group d) which is FULLY WITHDRAWN.
Fill in' the following table with the Ped / Rod Group number you wovid expect to see disolayed in each RWh window for EACH of the-situation"s la -c6 If nothing will appears write ' B1 snk . ' SITUATIONS
- *4 h <s)
50 mR/hr. - c. ...immediately evacuatin3 ALL personnel on the refueling floor to the 185' Changeferes.
- d. ...immediately evacuatin3 those personnel in the vicinity of the alarming ARM.(not the entire R/F Floor) to the 185' Change Area.
QUESTION 7.04 (1.00i fou enter HNP-2-1910 'Lors of All Plant Service Water', ano are unable to restore PSW o p e r a t i c'n . Subsequent operator actions require - you to plsce Fuel Pool-Cooling tn operation at naximum flow. This is done to ...(CHOOSE ONE)
- 4. ... provide a long-term hest sink for PHRSW vis the Fuel Pool Cooling Assist connection.
b.- ... prepare for the hi3h heat load from the i npendin 3 reactcr shutdown and required fuel onload.
- c. ... provide e lcng term heat sink for TSCCN.
- d. ... provide a short term heat sink for ROCCW.
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 26
~~~~R A5i5L55fEAL c5 TRUL'~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 7.05 ( .50) You -enter an area posted w2th the following sign
- CAUTION I Y
7.c5seen i
~ samationi -
..-MEEP OUT- . . - -
nwr ggsnea
'As a minimum, how often should you read your pocket dosimeter? -
0UESTION 7 .~ 0 6 (1.00) Unit 2.is operating-at 70% RTP; you notice power start to increase with NO CHANGE in recirculation flow or rod position. You suspect a Loss of Feedwater Heating. Wh'ich of the following actions are required / appropriate, per.HNP-2-1946?
- a. A 20% reduction in Recite Flow, monitored by Recire Flow Controller ma signal variance.
- b. 'A 20% Power Peduction, using Recire' Flow. monitored by APRM's.
- c. . Interiion of Eh:11ou Rods. to nea) nt Iin pr oper flux shape, pr2of to reducing Recirc Flow.
- d. Insertion of Power Rods, to maintain proper flux shape, prior to reducing Rec 2rc Flow.
F h e e 9 O l e 4 4 1 i i h- - ~ .
PACE 27 7 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND
~~~~Ed6f6[66fddE~E6 TR6E~~~~~~~~~~~~~~~~~~~~~~~~
GHESTION '7.07 (1.00)' A CAUTION-in HNP-2-1902, ' Pipe Break Inside Primary Containment'. states that:
, 'A-Pipe Break in the .Dr /well could result in Peactor Level-Reading inaccuracies due.to increased temperature.
Refer to Section 'E' ... for erratic correction method before proceeding. Erratic level indication could'be due to water in the sensing line flashing to steam.'
.Using Section *E', enclosed, and given the following readings:
2T47-R420 192 des F 2T47-R621 228 des F 2B21-404A +26 inches 2822-604B +23 inches
- What is the best esttmate of Actual u a ter Level?
- a. +9-1/2-inches
- b. +15 inches
- c. +3d inches d- +27-1/2 inches GUESTION -7.08 (1.00-Which of the following conditions establishes the reactor in HOT
' STANDBY. as defined bv HNP-2-1015 'h2intaining Hot Standbv Con-dition'7 CONDITIng PARAMETER (a) (b) (c) (di S & HS Sd HS S 1 HS S 1 HS Mode Switch N 212 deg F '
200 deg F 200 deg F Coolant Temp > 212 deg F 1040 psL3 1010 pstj 1010 psig ( 1040 psi 3 Rx Pressure 1.000 1.000 1 000 1.000 s K-eff OUEst:0N 7.09 <1.00) Both Recirculatton Pumps trip. (ou place the Mode Switch to SHUTOOWN but are, subsequently- UNSUCCESSFUL in resterting either Rectre Pump. COMPLETE-THE F0LL0utNG: fHHP-2-1?321
' Subsequent to Reactor Shutdown. and without both recir-culation pumps operittn3 watntain vessel level from '
(greater than) ____ (a'____. to ensure ____ b) ( ____.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 28 7.
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~~~~Ed6fdE65fCIL CU TR6E~~~~~~~~~~~~~~~~~~~~~~~~
GUESTION .7.10 (1.00)
.You_ receive the following snnunciator alarmi POWDEX SYSTEM TROUBLE You determine that you have a Condenser tube leak, per HNP-2-1928,
' Condenser Tube Leaks'. Which one of the following accurately describes your Operstor Actions?
- a. Confirm demin effluent < 0.1 umho/cmi increase power to maintain conductivity < 2.0 umho/cmi commence a reactor shutdown if con-ductivity > 0 5 umho/cm.
.b. Confirm demin effluent s 1.0 umho/cmi decrease power to esintain conductivity < 0.0 umho/cmi initiate fast shutdown if conductivity becomes '% 2.0 umho/cm.
- c. Confirm:demin effluent 1.0 umho/cm3 increase power to maintain conductivity ( 2.0 omho/cm3 commence normal reactor shutdown if conductivity becomes 5.0 umho/cm.
ds . Confirm demin' effluent
' -) .1 umho/cm3 decrease power to .
maintain conductivitv O.2 umho/cmi init:ste fast shutdown if conductivity becomes 0.2 umho/cm. QUESTION 7.11 (1.001
-Procedure HNP-2-1914, ' Torus Water Tempersture Above 95 deg F', directs!
'If any point indicates a torus temperature greater initiste torus cooling...'
then or equsl to o5 des F, Additionally.
'Operstor 2hov1d not initiste torus cooling unless water level is ___(1) ___
and at's level greater than ___(2) ___. Which of the following are the MINIMUM requirements for (1) and (2)?
- a. (1) Stable t2) that required for Natural Cirevistion
- b. (1) Increasing (2) Top of Active Fuel
- c. (1) Stable (0) 2/3 Core Height l
. d. (1) Increasing (2) Reactor Vessel Zero i
c. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 29
- 7. ~~~~~~~~~~~'~~~~~~~~~~~~
~~~~P____________
d626[6656dE"_66 TR6L GilESTION 7.12 (2 00) Pisce the following procedural steps from HNP-2-1001 into the proper sequence,.as they would be performed durIng an actual reactor plant startup and pressuri:Ption according to the procedure:
- a. Stabili:e reactor power with 1-1/2 BPV's open
- b. Start a Mechanical Vacuum Pump c.- Open the Steam Seal Feed and Bypass Valves
- d. Establish vessel water reject thru the RWCU System
- e. Place's SJAE into service f.- Start a Steam Packing E:<hauster 9
Place PCIC in Standby. per HNP-2-L125
- h. _ Start Reactor Feedwater Pump 2A (or 28)
GUESTION 7 11 (t.00)
. Procedure HNP-2-4207 'Trsnsformer Fire'. lists three (3) Operator Action Steps for a StartuP Au:,iliarv Transformer fire. Which of the following ts NOT s required Operator Actten'
- s. Confirm CARDOX system actuated.
- b. 1snusliy i t.s e t the requtred 0/G's and synchronize to the E-bus.-
- c. Deenergize the Transforner.
- d. Evaluate the , slant condittons for possible shutdown.
QUESTION 7.14 (2.00) Precedure HNP-2-1001r ' Normal Startup*. instructs the operator to: REAC water level select switch
' ulect level BJ level A to be used only when performing maintenance or surveillance r107E: FIGURE 2.?(2) IS on level B). PROVIDED AS REFERENCE EXPLAIN why level B is spectr.ad.
90ESTION '.15- (: 001 Procedure HNP-2-1437 'Peactor Sectreviatton Pum9 19eed Changes'. cautions the o p e r 2 '. x not to start an idle pump unless the other . ump t. r_ w r i*tng at - M*; loop speed. EXPLAIN the reason for t h i s e r x-e d u r a l CAUTION.
i *
-NORMAL, ABNORMAL, EMERGENCY AND RAGE 30 7 PROCEDURES ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~Ed656L66 6dL"65 TR6L GUESTION 7 16 (1.00)
Procedure HNP-2-1005, ' Power Changes', states that Unit 2's licensed maximum thermal power for steady state operations
'is 2436 MwT.
EXPLAIN in what instance (s) this maximum power may be exceeded cnd how this is verified. QUESTION 7.17 (1 00)-
~ HNP-2-9400, ' Jet Pump Integrity', identifies conditions under which-Jet pump integrity checks / calculations must be performed.
Which of the following IS NOT one of these conditions?~
- a. DAILY. with the Mode Switch in HOT STANDBY or RUN, and BOTH Recirculation Pumps running. -
- b. Following ALL Recirev13 tion Pump restarts.
- c. Prior to exceeding 25% RTP. ,
- d. Following any normal incresse in Recirculation flow greater than ,
20%. 7.13 ( .50) QUESTION HNP-2-1?$4 'Dost Accident Venting *, directs that Hydrogen and Oxygen concentrations must be strictly controlled. STATE the volumetric concentration limi',s for Hydrogen and Oxygen. GUESTION 7.19 (1.50) 0?r HNP-2-1020, ' Normal Shutdown'. LIST three (3) steps that the reactor operetor should take to DECREASE a cooldown tste that is too Past. ASSUME THAT THE 3HUTDOWN IS FROM HIGH F0WER CON 0!TIONS AtJD THAT THE BPV's.ARE FULLY CLOSED.
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;7. PROCEDURES - NORMAL,. ABNORMAL, EMERGENCY AND PAGE 31
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~~~~EI656L6656dL 66NTR6L E ____________________
GUESTION. 7.20 (1.00)
'After' station startup and synchroni:stion to the 230 KV line and partial-loading of the generator, 'WHAT' transfer (s) should be made to assure s*.ation house load supply?
NOTE: BE SPECIFIC WITH REGARD TO BUS / TRANSFORMER /ETC. IDENTIFICATION GUESTION 7.21 (1.00)
.Regarding the ' Loss of 125/250 volt DC Switchgear 2B (2R22-S017)'s Procedure HNP-2-1913:
EXPLAIN why the 'B' Recireviation MG Drive Motor is TRIPPED. 4 f n
e
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 32
-~~ EE5i5tBEiEAt E5sTR5t OllESTION 7.22 (1.00)
You sre given the dosimett- shown below. SEL EC T the ni e :: i niu ni r + dic t ioni level where i t it edrquate dosimci.rv . e;:c l ud a rig c TLD) F: s ITSELF. r Whole Body dose rate et 2.0 mP/hi.
- b. Wholt body dese rste of 2 0 . (- nif: 'h t .
c uhols Rody dose =t. of 200.0 mP/hr. C. WhaJe Body dose rate of 5.0 R/hr.
\
lit -st40!% t pc'tMits C ,, >
.l.l.I,l.l.l.l.l.I, ,
\
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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33 7.
~~~~65656L65566E~C6NTR6C------------------------
QUESTION 7.23 (1.00) Which of the-following is NOT required to be immediately verified or_ executed by the operator in response to a " Suspected Fuel Element Failure'. per HNP-2-1930?
- 3. Verify the Off gas edsorber bypass valve (F043) CLOSES on an Off-gas-Pre-treatment _high alarm.
- b. Verify the Off-sas stack inlet valve (F057) CLOSES on an Off gas Post-treatment high-high-high alarm.
- c. Lock out all the Drywell and Reactor Building Sump pumps until analysis can be performed, or the SS's approval,
- d. 00 NOT reject any reactor water to the Main Condenser or Radwaste without the SS's approval.
QUESTION 7.24 (1.00) Procedure HNP-2-1902 ' Pipe Bresk Inside Primary Containment *, lists r umerous conditions indicative of a bresk. Which of the following supports the suspicion of i SMALL bresk inside containment,
- a. Deccesse in. reactor water level: pressure ind/or temperature increase in Drywelli sirborne setivity increase in Drywell: increased DWFDS op+ratin3 frequency.
- b. Cecr4sse in reactor pressure; pressure and/or temperiture increase in Drywellt generator load decrease; DWFDS high level.
- c. Reactor Scram rrom low water level; pressure and/or temperature increase in Drywelli generator load decrease: increased DWFDS operating frequency.
- d. Reactor Scrim from high Drywell pressuce; generstor load decreasel 11rborne activity increase in Dtvwell: DWFDS high level.
t l
(. m Ls-i; NORMAL, ABNORMAL, EMERGENCY AND PAGE 34 f7, PROCEDURES TRUE~~~~~~~~~~~~~~~~~~~~~~~~
~~~~556f6E66f6dE"_66 00ESTION 7.25 (1.00)
The reactor is at power and the CR0 Svstem is lost. Per HNP-2-1940,
' Loss of CRD Systems'. if the operator CANNOT restore CRD flow, '
hs should....(CHOOSE ONE)
- s. ..., with reactor pressure less than 800 psig, and more than five.(5) accumulator trouble lights. conimence a fast reactor shutdown.
- b. ..., with reactor pressure'jreater than 800 psig, and five (5) odjacent accumulator trouble lights or thirty (30) . total trouble lights,inanostly Serem the reactor.
.e. .... with reactor pressure less than 800 psige and more than three-(3) accumvistor trouble lights. manually 9 erin the reactor.
- d. ..., 'with. reactor pressure greater than 800 psig, and three (3) adjacent -secomulator trouble li3 hts or 'htrty (10) total trouble i
lights.' commence a fast reactor shutdown, QUE3 TION ~.04 /1,00) Regarding H3tch procedures, in genarsi. EYPLAIN when you would ' eepect to see a CAUTION strtement AND.when you would expect to see i WARNING 1tatement. (Include the difference between the two)
. '00ESTION
.2~ (1.00)
Procedura HNP-501 ' Equipment Cleirance and Taggtng'. states:
'Und9r 4c !i r clim s t anC 9 5 t '3 Bnyon9 9Vef tothert:ed *c e> tach :r remove a red HOLD t?S *1*.hout first having a procer c l a.a r inc e . The only exception to tht5 i .i ...*/ CHOOSE ONE) 4 ...to 11: lit + OC systems of lesi t ha n 24 vdc.
- b. ...to-rac. Li eack out i ststion service feeder dreper c ...to 11olate witi-dt'.t1Lon21 power tetntretts::n circuits.
- d. ...ta rsch in/r ack out bor ties of 480 vsc. ." lesa.
V
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~ ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 35 8.
GUESTION- 8.01 (1.005 Which of the following scenarios requires ' application of the Power Transient fuel cladding integrity Safety Limit of the Unit i Tech-nical Specifications?
- a. Reactor power is at 32% PTPi the main turbine trips due to
.cn EHC malfunctioni the reactor SCRAMS on HIGH PRESSUREi the EPV's control pressure thereafter.
- b. Reactor power is at 70". RTP; a steam leak to the Drywell occurs and Drywell pressure rises; the teactor SCRAMS at 1 85 55138 HPCI
~
auto-actuation does not occur, but manual start is successfull the reactor is brought to a cold shutdown condition. c .- Reactor is in Start-Up, at 12% RTP; power is increased by rod pulli the reactor SCRANS at 12.5% power. by APPM's; level and pres-sure are maintained by normal ' systems for the plant status.
- d. The reactor is at 18 *. R T P i 1-1/2 BPV's are open in preparation for turbine warmupt controller failure reduces pressure to 875 psig; MSIV's closet reactor SCRAMSi level and pressure are maintained by normal svitens for the plant e t .s t u s . .
QUEST *0N 8.02 (1.005 Unit 2 is or-erating at 90% PTP. As part of the normal surveillance prog 3*, functional tests of the MSL Radiation Detectors are performed. (APPL .ABLE TS's ARE ENCLO5ED FOR REFERENCE) Given that 20ll-K603 A tests UNSAT, which of the following is most rRUES
/s) Establish a trip condition for the .:hannels fed by K401A within i hour. and be in STARTUP with the HSTV's CLOSED within 0 hourie or be in H0T SHUTDOWN utthin 6 hours.
'b) Establish a trip condition for the channeli fed bv K603A within I hour. and be in STARTUP with the MSIY'a CLOSED within 2 hours, or be in HOT SHUTOOWN withir. 6 hour s and COLD SHUT 00WN w i th in the ne>rt 30 hours.
(c) EstabitJh a trip condition for the channals fed by K603A within 1 hour, but you may continue in Operrttonil Condition 1. I1) Establish a tetp condition for the channett fed by K401A within 1 hour and be in at least HOT ShurDOWN within 6 hours and in COLD SHUT 00WN within the following 30 Tours.
r-_
+
CONDITIONS, AND LIMITATIONS PAGE 3d
8.
f ADMINISTRATIVE, PROCEDURES, I' ( .50)
.dUESTION :8 03 STATE who can declare the unit / plant to be in an emer3ency con-dition (classification).
NOTE .. Identify by Position Title and any special required qual-ifications. QUESTION 8.04 (1 00) Unit I Technical Specifications 45pecity the frequency intervals for the performance of Surve111snee requirements. This is accom-plished t,y usa of FREQUENCY NOTATION. COMPLETE the following Table. (D0 NOT INCLUDE GRACE PERIODS) NOTAi!ON FREQUENCY si S At least once per _______ hours. Q At least once per days. b) __,____ At least once per days. c) M _______ di At Isast once por 18 months. O!IESTION r.05- (1 50i
- f r. t t 2 Technteil Spectrications define SHUT 00WN NAPGIN as...
' Shutdown Margire shall be the imount of reactivity Du which the ri a': tor i s 'subc r i tic a l, or would be soberttic!1 from its present condition, assuming...'
L~if toe three conditions which complete the definition of SHUT-D0uu nARGIN. t J P
*~
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE' 37
- 8. ------------------------------
~
GUESTION' 8.06 '(3 00)
- c. .The following data was.taken or. Unit 2 during a single day of
'cperation at Operational Condition 1: Unidentified Leakage Ideratified Leakage 0400 5020-gal 604 gal Shift.1: 1020 gal 0800 4940 931 1200 5040 gal 900 gal Shift 2*
1600 5340 gal 1032 gal 5840 gal 1100 gal Shift 3: . 2000 2400 4640 gal 1248 gal Indicate any TS (or other) limit (s) that was(were) e:< c e e d ed .
/2.0)
. Justify your inswer(s).
b) What'is the definition of ' Pressure Boundary Leakage?' (1.0) l 00ESTION 3.07 (1.00) Temporarv changes to operiting procedures should be minimi:ed. Under which one of the following conditions is a temporary change perettted and warranted. as th+ proper corrective iction? a.- The addition of a CAUTION is necessary to prevent possible equipment damage.
- 6. A-correction is required to a valve /electrtcal lineup.
- c. The plant phvsteal :enditions assumed bv a pr ocedure are incorrect end prevent its completion as wrttten.
'd. A procedural step is determined to be unnecessarv and should be deleted.
l I l
I.
- 0. - ADMINISTRATIVE PROCEDURES, CONDITIONS. AND LIMITATIONS PAGE 38 GUESTION 8.08 (1.00)
Per Administrative Procedure MNT-01-0, 'Maintensnee Program', ENERGENCY-MAINTENANCE ...(CHOOSE ONE)
- a. ... is maintenance that must be performed to maintain safe operating conditions. as determined by the Operations Super-visor On Shift
- b. ... may be performed without issuance, o'r approval, of a
-naintenance Work Order (MWO). or procedure.
- c. ... must be approved by the General Manager or Deputy General Manager -AND- the OSOS or SS on duty.
- d. ... may be worked on 3 24 hour / day, 7 day / week schedule, upon the specific approval of the General Manager.
00ESTION 8.09 (0.00) Answer the following TRUE or FALSE questions with regard to the control of Lifted Wires and Temporary Jumpers (HNP-504 and HNP 0).
- a. A.tifted wire or jumper that is required cv Tech Specs, such .
as piscing an inoperable channel in the tripped condition. does (0 5)
.107 requLee PRB approval.
- b. When Itfting wires or installing jumpers not requiring a 'J and Lu' sheet, 'J snd LW' tags must still be placed on the (0.5) jumpers and/or lifted wires.
- . rhe final spproval to activate a 'J ind LW' clearance sheet on a safety system that is required to be operable by Tech Specs is provided by two members of the plant staff. one of whom must be a (0.5) licensed SRO.
- d. For surveillance procedures requiring the use of temporarv jumpers, independent verification is ONLY required on system (0.5) restorition and NOT on initial installation.
l
-----------___________[__.____._.._.'____
w .._h . ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 39 8. QUESTION 8 10 (1 00) HNP-501, ' Equipment Clearance and Tagging *, provides instructions for the proper method of requesting and issuing clearances and hold tags. .W hich of the following accurately describes the clearance process? ^ 4 When a maintenance project will require a clearance for more than one shift,-the Shift Supervisor can release.the sub-clearance to the
' Maintenance Foreman't by name release is not required in this case.
- b. Any clearance which requires the normal electrical lineup of the plant to be modified, will be issued by the Shift Supervisor in the form of written Switching Orders, per HNP-X-1646.
- c. If'a new HWO has identical isolation boundaries to a previously released MWO/ Clearance, the new NWO may be added to the clearance.
- d. When re< storing a safety-related component to service, if NOT covered bv procedure or surveillance reqvtrement. INDEPENDENT VERIFICATI0tl of the relevae is AEGUIRED.
QUESTION 3 11 (1 00) Procedura MNT 01-0, ' Maintenance Progrim*. designstes certain responsibilities for the Shift Supervisor in returning components / tystems to service after maintenance activities. Which of the following is fl0T one of these responsibilities.?
- s. The Shift Supervisor will EVALUATE the inspections and tests performed to determine if the system or component mav be returned to service.
- 6. rhe Shift Supervisor will PLACE the avstem or component in operation and 00CUnENT its operational status bv signing the NWO.
- c. The Shtft Supervisor will attach a copy of any LCO report gen-orateo as a result of the work activity to the nWO p ack age. once the HWO is closed avt.
- d. If the oparstional *eut(4) are UHSATISFACTORY. the Shtft Super-visor will return tha MWO. with amplifying remark 5 to the maintenance Foreman in cuteje of the work act vity. to allow for further cor-ractive maintensn:s to be performed.
C .
's: l r
w , PAGE. 40
- 8. ADMINISTRATIVE-PROCEDURES, CONDITIONS, AND LIMITATIONS 4
. QUESTION 8 12 (tiOO)
Unitc2 is in : Oper ational ~ Condi', ion 1, at 75% RTP, with two outstanding deficiencies ll AOS 1 ADS Valve INOP (1 Day) CS CST.Svetion INOP (3 Days) The Auto - swip of the HPCI suction upon receiving CST low level is
~
determined to be UNSATISFACTORii_ The suction is MANUALLY switched
-to'the Suppression Pool, and the suction to the CST is. ISOLATED.
The Shift Supervisor determines that the required action (s), per the Unit Technical Specifications is(are) ...(CHOOSE ONE) NOTE: APPLICABLE TS's ARE ENCLOSED FOR REFERENCE 4 ...no new limitations or TS Operational Condition restrictions
~
are initiated by this re-alignment.
- b. ...be in at-least HOT SHUTDOWN within 12 houri ind reduce reactor ,
steam dome pressure to less than or equal to.150 psig within the foi-lowinj 24 hours.
- c. ...be in .st least HOT SHUTOOWN within 4 hours and COLD SHUTOOWN
- within the following 30 hours.
- d. ...be'in at least HOT SHUT 00WN within 6 hours and reduce reactor stosm dome pressure to less than or eqori to 150 psig within the nent':30 hours.
G 1 t h b
.--.x---_=.
m t 4 PAGE 41
~
8.- ADMINISTRATIVE PROCEDURESr.CONDITIONSr AND~ LIMITATIONS QUESTION = 8 13 (1.00)
~ Procedure HNP-514,=' Control of Locked Valves'., states.that . ..
' ...~ Confirmation of valve position is required periodically ... fand) all valves will.normally
.be' checked and manipulated by Operations Depart-eent personnel ...'
What is the proper way to CONFIRM a locked valve position?
- a. Turn the valve hand wheel in the OPEN directioni confirm the lockingfdeutce integrity.and proper installation by visual inspection.-
- b. Turn the valve hand wheel in the CLOSED directioni confirm the
' locking device integrity and proper installation by attempting to misposition the valve.
- c. Turn the valve hand wheel in the DESIRED POSITION directioni conftem the lockine device integrity and proper installation by viavat inspectton.
- d. Turn the silve hand wheel in the DESIRED POSITION directioni confirm the locking device integrity and proper installation by att4mpt.ing to misposttian the velve.
l [ l I l I l i _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ - . _ _ - . = . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - - _ _ _ - . _. ____ _ _ _ _ _ _ __ 1 _ _ _ . _ . _ . _ _ . _
7 c PAGE 42 ADMINISTRATI6E' PROCEDURES, CONDITIONS, AND LIMITATIONS 8.
'GUESTION 8.14 (1.00)
Unit 2 is.in COLD SHUTDOWN during a reactor strartup with no cutstanding deficiencies. Hydrogen Recombiner A becomes INOP. It is anticipated that repairs wt11 be complete within two (2) weeks. The Shift Supervisor determines that the required action (s) per the Unit 2 Technical Specifications is(are) ... (CHOOSE ONE)
- a. ... Operational Condition 4 must be maintained (Entry into Operational Condition 5 is acceptablei
- b. ...Startup activities may continvei Operational Condition 3 may be entered, but not exceeded.
- c. ...Startup. activities may continvei Operattonal Condition 2 l
cay be entered, but not excaeded: Oxygen concentration shall be Oaintatned / v/o.
- d. .. 3tartup ictivities may continvei Operational Condition 1 and/or 2 may be entered. but the Recombiner must be returned to an GPERABLE $tatus within 30 davs.
NOTE: APPLICABLE TS's ARE ENCLOSED FOR REFERENCE GUESTION 8.t5 ( .50' Given the following conditions on Unit : r* ode Sw t tch - Refuel Temperstore - 180 des F ' Pressora - O psig Level - 35 inches PHR - SDC Mode Head bolte to the RPV are DETCHSIONEO STATE the abova 1escribed Operational Condttton. I l i
6
-ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 43
~8.
OUESTION 8.16 (1.00) HNP-507, ' Control of Operator Aids', provides guideance on the use of Information Tags. Information Tags ...(CHOOSE ONE)
- o. ...may supplement safetv tags to protect a piece of equipment, but cannot serve as personnel protection devices.
- b. ...shov1d be used whenever a piece of equipment is physically removed from its normal position. encept'in the case of calibration and/or maintenance.
- c. ...can be label tape notes on annunciator windows to denote en MWO request date. These do not require tracking.
- d. ...shall be used in the Main Control Room, on the Refueling Bridge. and on Local Operating Panels only.
QUESTION ~8.17 (1.00)
. Procedure HNP-511, 'Public Address Notification Signals', lists five (5) plant emergency conditions for which the public address system is used to announce. Which of the following IS NOT a condition having a DESIGNATED TONE.
- a. FIRE in the Diesel Butiding.
- b. 'N00E' Radiological Emergenev declaration.
- c. SOMB THREAT received bv Control Room p+rsonnel.
- d. ' GENERAL EMERGENCY
- Radiological Emergencv declaration.
CUESTT0N 0.18 (2,50)
'lo t t ! Tachntcal Specifications provide guidesnee with respect to refueling operations. COMPLETE the following. es per U1 TS's.
- i. 'Jhen conduc ting refueling oper a tions , at least
___.1)___ 3Rn channels must be operable and ___i;) ___. with s minimum acceptable count rate of ___ (3) .__. Refueling operations may commence '2 0) (4) ___ after reactor shutdown.
- b. TRUE or FALSE You are conducting a sptrst reload on Unit 1. Up to four (4) fuel assemblion will be loaded into their provtous core posttions nent to the four (4)
SRM's. Until those assemblies have been loaded, the (Minimum Roqvtred) 1RM count rate reqvtrement (0.5) is not necessary. _ _ _ _ _ . _ __ E
r_ U b
-.i i ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATI0N'S PAGE 44 8.-
QUESTION 8.19 (4.00) Unit- 1 Technical Specification 3.6.F.2 establishes the following conductivity and chloride Itmits* PLANT CONDITION CONDUCTIVITY LIMIT CHLORIDE LIMIT 5 umho/cm ' O .1 ppm
> 212 des F/Pressuri:ed w/o Steam Flow 2 omho/cm 0 2 ppm
> 1% rated steam flow
- 4. Per the TS basis, WHY is the chloride limit more restrictive at the lower steaming rate than when at power? (1.0)
- b. STATE the conductivity and chloride limits which require Unit 1 to be immediately shutdown and placed in a Cold-Shutdown condition. (t.0)
- c. WHY, per the TS basis, is COLD SHUTDOWN the most desirable con-dttion in which to piece the reactor when the out-of-spec limits in (1 0) part (b) are reachedS 4 WHY, per the TS basis. ti it unnecesserv to merform frequent chloride measurements as.long is conductivity is continuously (1,06 coni +cred :end wtthin its normal range?
00ESTION B.20 (2.00)
- s. Unit 2 12 in Operational 1 Condition with N0 outstanding deficien-etes. The current Surveillance Assignment printout sheet identiftes a
'Liteit 04te' for the PCIC quarterly flow teste but the FCIC system becomes INOPERABLE before completing the sorvet11ance. SELECT the statement which accuratelv desertbei the servettlanca requirements is per HNP-831 ' Tech 3ppe Surveillance Progr)m.' (1.0)
(1) The toeveillance must be performed immedt7tely AFTER returning the tvstem'(or subsvstem n to an OFCRABLE condition. (2) The r.eut regular surveillance intervil 1h411 commence UPON THE COMPLETION of the overdue ivrveillanco. I ') ) The avrveill1nce th3L1 NOT be documented is officially miined untti the END of the 'Litest Date.'
*4) Since the FC*C svitem ti s ir e 3dv D80PCF AELC , in LCO sheet need NOT be issvec to
- rick the missed survat113 nee.
D. The 'Eiriteit Oste' ble t of the Survettlince Assignment printout s herat reads '00000' fo, c 9t.en iveveillwnee. 3 RATE the meaning of
't.0) this re14tng ANO for which Unit tt would be appiteable.
e - d, 3 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 45 8.
-QUESTION 8.21 (1 00)
Unit 2 has been recently shutdown and placed in COLD SHUTDOWN -
' Operational Condition 4. The shutdown /cooldown was necessitated by a requirement to drain and visually inspect the Suppression Pool.
The following plant conditions / requirements have been established! CS system is'sligned to the CST Reactor Mode Switch is locked in the Shutdown Position No maintenance affecting the reactor vessel is in progress There is one outstanding deficiency: D/G OA Turbocharger is undergoing repairs (D/G INOP) NOTE! APPLICABLE TS's ARE ENCLOSED FUR REFERENCE The shift Supervisor may ...(CHOOSE ONE)
- a. ... commence Suppression Pool draining, since all TS LCO require-cents are met.
- b. ... commence Suppression Pool draining af soon as he ensures that NO POSITIVE REACTIVITY changes will occur during this condition. .
- c. ... commence Suppresaton Pool draining as soon is he ensures that NO POSITIVE
- REACTIVITY changes will occur AND that one LPCI subsystem ts OPERABLE in this .:ondition.
- d. ...commenee Suppression Pool draining only AFTER the D/G 2A Turb; charger is repaired and the 0/G declared OPERABLE. ,
OUESTION 8.00 (1.00) With regard to Procedure HNP-ADM-0903, *r micol of Pulled Annun-c13 tor Cards': EYPLAIN how an operator can determine iS i particuinr Annuncistor Card is pulled. WITHOUT looking at the r ulled Annunciator Card Control Sheet or Incen. .
i - . c6Py
- j)l f~
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 46 5. y-------------------------------------- ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN ANS4EF 5.01 (1.00) d REFERENCE E IH , L - P G"- 6 0 '5 (15) i ! ANSWEP 5.02 (1 00) a REFERENCE ETH. L-RO-602 t AN3WER. 5.03 (1.00) d FEFERENCE Cener a1 Elec tc ic. NEDE-24010 *Jun 81) ANSWER 5 04 (1.00) 1 REFERENCE itoim Tibles ANSWER 5 05 (2.00) (2) - Stirtin3 Fump 2 (0.5)
- 1. (0,5)
- b. Cyrve B
* (0.5)
- c. ItiC RE ASE (0.5)
- d. Curve C FEFERENCE Fump Laws
-._ ___ _ 4
i e
- 5. THEORY'0F NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 47
~ ~~~I55E 5 66 YU AU C5~~~~~~ ~ ~ ~ ~~ ~~~ ~ ~ ~~~ ~ ~ ~ ~ ~ ~"
C.NSWERS -- HATCH 1&2 -85/03/11-K E DROCKMAN ANSWER 5.'06- (1.50) F1. b L F2. -e F3. a L1. c L2. a L3. b- (.25 each) REFERENCE EIH, .GPNT, Vol VII, Chapter 10.2-23 ANSWEF' 5.07 (1.00) d d REFERENCE ! EIH. L-RG-667 (3), L-RO-654 ANSWEP 5.08 (1 00) b - 0F - 0 REFEREHLE . l I EIH. GPNT,Vol VII, Chapter 10.1-03-86 1 ANSWEP 5 00 (1.001 a REFERENCE EIH. L-RO-675 ANSWER 5.10 '2.50)
- a. Recirenlation Pump Trip (Lo Lo Level)
- b. MSIV Clos. ore- ( L t. Lo Lo Level) - O P - C V C l o t u r e w / F:F'V F . S .
- e. HPCI # RCIC Ir.jpet f or.
r 45 03 a r C F:CI C C oc. } rJ c.w r E f f * : t r (Ste,6 f C r.l de r Wrter)
- e. F'e e i r c;ol a t t ori F on.p Fi vreb e c i I41 E.L.1 (0.5 och)
T z.- .
, , =q <
T, D
\ ',,1} ..
/
'I ,,
_3 '\ 5 ' i PAGE 48
- 5. THEORY OF NUCLEARLPOWER PLANT OPERATION, FLUIDS, AND
--- iiiE RR 5 5J ...-s U RiE s---Si----~ ~--------------------------
ANSWERS -- HATCH \1E2
- i. -85/03/11-K E BROCKMAN g M 1 ,;
REFERENCE -
.EIH, L-RO-732-o .y ANSWER 5 11 (2 50) 1 1
'\ 0 i 6.g }Natur.a1 Cireviation at reduced power (Scram) due to the tripped RRP's " o bi '; Decreased suction f ron - the downcomet (Increased voiding in the core causing a swell in the downcomor)*
l.. c .In response to level increase , \ 5 (
'd.-' Loss.of FW Heating (due to reduced e:-: traction ssteam flow) e .- EHC established flow appropriate to control pressure ( 0.5 etch)
' Flow equivalent to reactor power) s
- REFEF:ENCE EIH, L-RG-732 4 .
ANSWER' 5.12 (1.00) b y , 1 l
--REFERENCE ,
y E7H, . L-PG-667 ( f O p.t T ~\ c
+ s oc i
I ANSWER 5.13 4%
'a' P % tst c\ s
- b. (1)
REFERENCE
-EIH,'L-RG-672-(15); U2 TS 3.2.3
-ANSWER 5 14 (1.00) d REFERENCE ,
EIH, L-RO-602 (9) H c
\
F g
ci . THEORY OF' NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 49 5. ANSWERS -- HATCH 1&2 -85/03/11-K E BROCKMAN CNSWER 5.15 ( .50) FALSE.
-REFERENCE EIH, L-RQ-603 (4)
ANSWER 5 16 (2 00)
- a. INCREASE
- b. DECREASE
- r. INCREASE
- d. REMAIN THE SAME REFEFENCE EIH,'GPNT. 'l o l .. II , Chapter 10 2 o
ANSWEP U.17 (1 001 b. REFEREriCE EIH.. Thermodynamics L/P, pp 52-56 ANSWEP- 5.18 (2.00)
- s. 2 b, 3 (Gr. as appropriate for answer 3tven-in 's)) .
REFERENCE EIH. GPHT, STA Traintn3 Manual, Section 9:
FV THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND- PAGE 50 5. y ggggg-------------------------------------- ANSWERS -- HATCH 1&2. -85/03/11-K E BROCKMAN ANSWER 5.19 (2 00)
- 4. By observing the Full-in and Full-out travel lights (the CPerator could determine if geometric distoetion had occured.
' Inability to. conduct. full detector movement would indicate (1 0) that internal misconfiguration had occured).
- b. By observing the neutron level while moving the nuclear instrumentation. A significantly HIGHER (approximately 300 times) count rate would be seen for the UNVOIDED areas of the (1.0) core as opposed to the VOIDED.
REFERENCE EIH,L-RG-540 (M.8) ANSWER 5.20 (1 00) REFERENCE c EIH+ GPNT, Vol. II, Chapter 3.E; Nuclear Power Svstems Handbook, Harrer & Beckeriv. p 44. ANSWER 5 21 (2.00) a.- lambda = Ln 2/T = .6o3/55 6 = .0125 see E -1 1/2 (CALC NOT' REQUIRED)' T =-1/-lambda'= 1/ .0125 = - 80 see After t. h e initist prompt drop, power c: sono t dec r ea se f as ter than the longest lived delayed neutrons apposr (10) b, ihorter (0.5) The initial prompt drop will oniv be due to prompt neutrons.(0.5) -OR- Decay of short lived precursors (0 5) PEFERENCE EIH, GPNT, Vol. VII, Chapter 10.1 L
'9' PAGE 51
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION ANSWERS -- HATCH 182
-85/03/11-KOCKMAN E BR ANSWER. 4.01 (1.00) b REFERENCE EIH, L-RQ-752, DCR 80-111; L-RG-734 ANSWER- 6.02 (1.00) a REFERENCE EIH, L-RO-752; DCR 81-175; GPNT, Vol V, Chapter 4.5; GPNT, Vol VII, Chapter 8.1 ANSWER 6 03 (1 00)
C REFERENCE RIH. CPNT- Vol VI, Chapt.er 7 2; EIH Simulator
. ANSWER 6.04 (1.00) e REFiRENCE 9, Chapter 4.1-92 GPNT, Vol VI, Chapter 5.5-10; E!H. GPHT. Vol GPNT. Vol VII. Chapters 9.2 2-11 and e.2.3-5 ApSuER .!.05 (1.00) c ,
REFERENCE EIH. GPNT, Vol V, Chapter 4.1-23
' ANSWER 6.0e (1 00) d b
c
- 6. PLANT SYSTEMS DESIGN, ' CONTROL, AND INSTRUMENTATION PAGE' 52
' ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN
. REFERENCE EIH, GPNT, Vol V, Chapter 4.3-12 ANSuEP 6.07 (1 00)
.s REFERENCE EIH. .CPNT, Vol V, Chapter 5.1.II.D ANSWEF- 6 08 (2.00) ,
- a. To prevent a loss of reactor water inventory to the Torus (0 8) through the Minimum Flow Velve (0 2)
- b. SDC PCIS Valves'(F008 F. F009) -
Auto Close All running RHR Punipt - Trip Head Spray Vsive (F0231 - Auto Closes
'RHP Inboard Inj. Vi l v(- (f0:57 -
A s.it o C l o s e s (2 ree,'d (d 0.5 rech) REFERENCE EIH, GPNT, Vol V, Chapter 4.4-15,17: GPNT, Vol VI, Chapter'8.3.c.37 HNP-2-1114, p6 AUSWER 6,00 12.004 E, 1 05 psig (.25) in D yuell (.25) rnd/or .Lo Lo Level (.25) of - 55 inches (.25)
- b. (1) WILL (2) u1LL (3) WILL NOT (4) WILL (.25 nach)
REFERENCE EIH. GPNT, VOL VI, Chapter 81 ANSUER 6 10 (1.00) b REFERENCE EIH, L-RO-733, p11, Fig 4
6.- PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 53 ANSWERS -- HATCH 1&2 -05/03/11-K E BROCKMAN ANSWER 6.11 (1.00) C REFERENCE-EIH, L-RG-752; DCR 70-442; HNP-1-1500 ANSWER 6.12 (1 00) b REFERENCE- - EIH, GPNT,. Vol VI, Chapter 5.37 DCR 83-87 ANSVEF 6'.17 (1 00) b - OP - d REFERENCE
'EIH, GPNT,-Vol. V, Chapter 4.1-26; L-RO-714 (14)
ANSWEF 6.14 (1.00) d REFERENCE LIlh .L-PO-71c (6r9);-L-RO-700 (10) l ANSWER 6.15 (1.001 b
. REFERENCE EIH, L-RG '04-(6) i r
I j. i-I. o
ta.
?;
1 7 6.- PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 54 ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN ANSWER 6.16 (2.00) PARAMETERS MONITORED Vessel level is monitored-ind becomes the controlling signal for operation of the Startup Level Control (F111) valve. (0.5) dP signal scross the SLC Bypass Valve (F110) is monitored ind becomes the controlling signsi for RFFT speed. (0 5) SYSTEM / COMPONENT CONTROL The input to the M/A stations is a dP error signal from the dP controller. The controller senses the dP across the F110 valve, compares it to the controller 1st dP, in order to maintain a constant dP across the valve. (0 5)
.Tne F111 valve opens / shuts in response to reactor vessel water level. When the valve opense the dP decreases and the signal sont is to increase RFFT speed; valve closure ts the converse. LO.5)
REFERENCE EIH, L-PG-726 (1,5,6) ANSuER 6 17 (1.001 INCREASE :0.5) The vacoom breek er prcvides a direct ,oth to the'DRiWELL. (0 5) PETEPENCE EIH. GPNT, Vol V. Chapter 3.1: NUPEG/BR-005/Vol 5. do 4 Power Resctor Events, Jan 84, p 5 (Hatch occurance 8/25/82) ANSWER 4.18 (1 00P
-b REFERENCE EIH. GPNT, Vol. VI, Chapter 5.1-25, 26 ~. 7
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 55 6.-
-C.NSWERS --_ HATCH 182
-85/03/11-K E BROCKMAN
-ANSWER 6.19 (2.00)
Level would be LOWER. (0.5) Since measured steam flow is less than feedwater flow (0.25), an orror signal is generated (0.25) which tends to decrease RFP
. speed.(0.25). A lower vessel level generstes an opposite error Level signal (0.25) which tends.to increase RFP speed (0.25).
will stabili:e when the error st3nals are equal. (0.25) REFERENCE EIH. CPNT. Vol . '/I, Chapter 5.1 ANSWER 6.20 (1.00) d REFERrNCE
- EIH, HNP-r-1001; ANSWER 6.21 (3 00)
( 2) (b) (c) 03 03 04 ROD GROUP It!GERT ERROR 22-51' 22-51 18-03 INSERT ERROR 46-55 46-55 46-55
~3 4 -2.7 Blank Glank (.25 each)
WITHORAW ERROR REFERENCE ETHi G P N T , 'J o l . VII, Chapter 0.2,2 e _g
l 4 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 56
- 6.-
ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN ANSWER 6.22 (2.00) RED' - Solenoid control.vsive has enersi:ed (0.33); De-energi:ed (0.33) GREEEN - Power available to the solenoid control valve (0.33) Energi:ed (0.33) AMBER - Pressure in tailpipe (185 psig)
~
(0.33) Energtzed (0.33) REFERENCE EIH. GPNT, Vol. VI, Chapter 5.1.II.B.2 ANSWER 6.23 (1.00) e REFERENCE , EIH,'GPNT, Vol. VI, Chapter 5.5-2; Vol. VIIr Ch3Pter 9.J-t?.
.0 I
\
k _w- - _ _ _ . - - . . . . _ . - - - - - - _ - _ . _ _ _ _ _ _ _ _ _ - . _ _ _ - _ - - _. __ __ _ _ _
,t :
E PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 57 7.
~~~~R I656E6656dE~C6NTR6[~~~~~~~~~~~~~~~~~~~~~~~ '
C.NSWERS -- HATCH 142 -85/03/11-K E BROCH11AN ANSWER 7 01 (0.00) ~ (0.5) a) 1.'RPV level cannot be matntained
- 0. Suppression Pool-water temperature cannot be maintained (0,5) below 110 dea F b )' 1. Five (5), or more adjacent control rods not inserted below (0 5) the 06 Position 2.: Thirty (30), or more total control rods not inserted below (0.5) the 06 posttion.
REFERENCE EIH. HNP-2-1900 ANSWER 7.02 (1.50) s) POUTINE to.5) ! (0.5) b) REGULAP I c) BLArlKET (0.!> REFERENCE EIH. HNP-8008, pp 1 6, 8
'ANSWEP 7.00 (.1.00) c
-REFERENCE ECH. HNP-2-1903, p2 AriguER 7.04 (1.00) d REFERENCE EIH. HNP-2-1?10 ANSWEP 7.05 t .50)
Every (Lvo (5) mtnotes 't/2 credtt for more ':onservittve response' t
I
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND FACE 58
~~~~R d656[66564[~6 NTR6[~~~~~~~~~~~~~"~~~~~~~~~ l ANSWERS --' HATCH 1&2 -85/03/11-K E BROCKMAN REFERENCE ' - EIH. GET Handbook, P25 ANSWER 7 04 (1.00) b REFERENCE EIH. HNP-2-1944 t
ANSWER 7.07 (1.00) b i REFERENCE
~EIH. HNF-2-1902 e
ANSWEP 7.08 (1 00) a :
. REFERENCE EIH. HHP-2-1015 ,
ANsuER 7.09 (1.00)
) * $70
- rrom 'les sel 2ero -GR- + 53' from Instrument Zero /0.5) b' (a flow path for) Natural Cireviation (0.5)
PEFEPENCE CIH. HNo-2-ic% ANSWEP 7.10 it.00) d , ! FEFEFENCE EIH, HNP-2-1928 l P l
-._____.t____
f. L ;. 7 .' PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 59
~ ~ ~ ~ ~ " " ~ " ~ ~ ~ ~ " " ~
" "RI656E66f65E~C6NTE6L ANSWERS -- HATCH 182 -85/03/11-K E DROCKMAN ANSWEf 7.11 (1.004 c
REFERENCE-EIH, HNP-2-1934,p1 LCNSWER 7.12 (2.00)
~
d (.25)I f, c, b (.75)# 0.(.25)I h (.25)I e (.25)I a (.25) REFERENCE EIH. HNP-2-1001, pp 18, 19, 20 22 23 20, 29 ANSWEF: ?.13 (1.00) a REFERENCE CIH, HNP-2-4207, p2 ANSWER 7.14 (2.00).
'O' is nor nia lly tr. lec t c d because a f silor e in the 'A/C' 52de, causiris the transa.ittert to. sense a LOW 1evc1, would ccuse the following!
A tutbine tr_ip on High Level (59') would riot occut (O.Es If 'A' transmitter were selectedt a falso signal would be sont out to the controllet t to stieretSc levtl (05). Level wovio continue to increate until the operstor tern.2neted the trentient with 'D' selected. e fattore of the 'A' trrnsmitter would not ttsult in level charest 5 3 rice the '0' t i ensn-1 t t s i htt ren t teiled. (Out still do not havn out of 3 trtp .tv: 211bler (0.5) Failure of ' D ' t r e ri n n. i t t e t w i t t.
'O' selected would edure wrtar level change. but the 2 out or 1 trip would still pr ovide (0.5) pr ot ec t iore.
,' ?
PAGE 40
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND
~~~~5X656E665CIE~CUNYRUE~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- HATCH 142 -85/03/11-K E BROCKMAN REFERENCE EIH, L-RG-7268 GPNT, Vol VI, Chapter 5.3 ANSWER 7.15 (1.00) To preclude establishing excessive stresses in the jet pumps. due to flow reversals - OR - to prevent excessive radial bearing loads (on the rectre pumps) REFERENCE EIH, HNP-2-1417,'p58 GPNT, 901 V. Chapter 1.1 ANSWER 7.16 (1.001 Mantmum Ltcensed thermal power m.sv be exceeded in the instances of THERMAL SPIKES.(0.5) Verificetton is accompitihed bv use of 00-1 Printouts from the Process , Computer.(0.5) REFERENCE EIH. HHF-0-1005. pp 1,2 , ANiuCA 7 17 (1 00) d PEFERENCE EIH. liNP- '8400 11 2 TS '3.4 1.0 A93uEP 7.10 ' .505 H-2 - 3 v eo 0 - 7. - 5 v/o GEFERENCE EIH, HNP-2-1906 -
PROCEDURES - NORMAL, ABNORMAL, EMERCENCY AND PACE 41 70
~~~[II6f6C66f65C~660TR6C"~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN ONSWER. 7.10 (1.50)
- 1. Shut down the in-servtco SJAE. (Place the MVP in service) ,
- 2. Shut down the running RFP. (Control level with RCIC)
- 3. Temporsrily discontino.# :ontrol rod insertson. (0.5 each)
REFERENCE EIH. HNP-2-1920
' ANSWER 7.20 (1.00) 4 1 4 0 .9 Buses 2A Jnd 28 should have their startup supply trins-former swapped from Startup Transformer 2C to Unit Auxiliary Transformer 2D. (0.5) .4140 V Buses 2C and 20 thould have their startup supp1v transformer transferred from Startup Transformer 70 te. Un1t Ausitsery Teinirormer 2A. (0.5) ,,
TEFERENCE C Iri . NHF-t -t No AHSuER 7.21 (1.00) Trtpptnj the Drive Motor wt11 prevent MC ist damaJe during coJst- , doun' O . 5 in the event tnst the AC pumps are lost some time 1 : t .+ r ind the MG Set trips. (0.5) - FCFERENCE I E,tH. HHP-2-tot 3 . v.ngutp 7 . 2 ,. (1.00) 6 REFCRENCE CIH, GET Handbook. pr. 25, 20 ANSWEP 7.23 '1.00$ 4 r i i
s' t PROCEDURES - NORMAL, ABNORMAL, EMERCENCY AND PAGE 62 7.
~ " ~556I6[66iCIC~C6 Yi6[~~~~~~~~~~~~~~~~~~~~~~~~
CNSWERS -- HATCH 1&2 -85/03/11-K E BROCKMAN REFERENCE EIH, HNP-2-1410' RNSWER 7.24 (1 005 4 REFERENCE EIH, HNP-2-1002 i
.1 005 CNSWER ?.25 c ,
REFERENCE E IH. HNP-2 .1040. p t e AN3WEF 7 26 1.1 00) l CAUTION - Equtpment dama.j tng condt t tons .m t a t so.!) WARHING - Personnel injury he::ards entit (0.55 pef *EPEHCE ETH. HHF-2 .p 25 AN94ER 7 27 (1 00) b
#EFERENCE EIH, HNP-501. pe, 8 15 t
e e l
PAGE 43
- 8. ADNINISTRATIVE PROCEDURESe CONDITIONSe AND LIMITATIONS '
ANSWERS .. HATCH 142 -85/03/11-K E BROCKMAN
. ANSWER 8 01 (1 005 ,
3 REFERENCE EIH, U1TS, 1 1.c
-ANSWER G.02 (1.00) e REFERENCE EIH. U2 TS, 3.0.4, 3.1 1 3.3.2 ANSWER 8.03 ' 50' SHIFT SUPER'1ISOR (SS) or OPER ATIONS '31)PER'/ISOR (0503) or ANY HIGHER RANKING LICENGED OR CERTIFIED PERSON PRESENT ,
REFERENCE EIH. HNP - 4520, 4620e 4700 .. ; ANSWER 8 04 (t.00) m) 12 hour s ( + 0) , hi 11 4.s y s (+ 0) e). 31 days- (+ 0) (.25 each) d) R PEFEPENCE FCH. U2 T9 T3014 1 13 HHP-0-ADM-0831 ANSuER 6.05 (1 50)
't) H1jhest worth rod (0.25) fully withdr awn '0,;5)
I2' tenen free
'1) Cold (48 dej F) (0.5 esch) ,
REFEPENCE FIH. IJ: TS, 1.0 *10n' -m._ i
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LINITATIONS PAGE 64 ANSWERS -- HATCH 182 -05/03/11-H E PROCT: MAN CNSWER B.06 (3 00) a) UNIDENTIFIED LEAVAGF increased fron. 4 2 . 51 g p na rate at 0400 tc a 4. 50 syn, i e t s. it 2000 thtet e::ceeding t he 2 g y n, 2ncteete 11n2t wtihin a Oc hi m r, period. (0.67)
TOTAL LEAMACF e,tceeded the 25 gpni 11 se i t over 3 24 hoter Pe-tsod (25.50 spn) (0 66) UNIDENTIFIED LE Ak AGE e):ceeded thc 5 spne l i ne t t at 2400 (5 2 3Pni) (0.67) , b) Pr es sur e Bounda r y Lea't age it leafagn through c non-isolable frolt (0.5) t ri a reactor e nol a rit tvnten, c o n.p o rie ri t teody , pipe wrll. or vessel wall (0.5' '1.0) REFERENCE E.IH. U2 TS, 1.0, 3 4.3.2f Confirnictory Order 75?O-01, dtd 7-8-G3 ANSWEF B.07 (1.00) a - OR - C R EF E r:E t> E E (IH. HtJP -9. pa7 ANSWEF 8.08 '1.00) b REFERENCE EIH. HUT 01-0 pe ANSWCF B.0c (0.00) a) TRUE b) TRUE
- c. ) FALSE
- 6) TFUE PCFERENCE EIH, HNP-504, pp 1+?; Htli-9. p:S
ADMINISTRAT19E PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 65 8.
-85/03/11-K E BROCHMAN CNSWERS -- HATCM 182 CCSWER 8 10 (1.00)
C REFERENCE EIH, HNP-501, pp 1, 2, 9, 10 ANSWER 8 11 (1.00) d REFERENCE EIH. MNT 01-0, p20 ANSWER 8.12 (1.00) , 4 REFERENCE EIH U2 TS, 3 5.1, and 1.5.2 8.13 (1 00) . ; ANSWER D , RCFERENCE FIH. HNP-514, p1 ANSWEF 6.14 (1 00) d REFEPENCE EIH. U2 TS, 1 0.1 3.0.4, 1.6.6.2 i: ANSWEP' 8.15 ( .50)
~
'Ortooliny'
PAGE 64 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 8..
-85/03/11-K E BROCNMAN ANSWERS -- HATCH 182 REFERENCE
'EIH, U2 TS's, Table 1.2 A::SWER 8 16 (1 00) c REFERENCE EIH, HNp-507, pp 2, 3 ANSWER 8 17 (1.005 b
REFERENCE EIH, HNP-511 ANSWER 8 18 (2.50) e
.s . (1) 2 (2) fv11v inserted (3) 1 ep 5 (4) 24 hours
- b. TRtlE REFERENCE EIH, Q1 T9, 3 10.C.1, 3.10.C.2, 3 10.H ANgucp g.io 44.00)
- a. Because the dissolved onvgen content of the reactor coolant is typtcallv higner during low steaming rates (e.g. Startup of Hot ft.0) 9tandDy1
- b. Conductivitif -
10 'umho/cm (975 des C) (1 0) Chloride - 0.5 ppm
- c. The lower temperature reduces the corrosion ratos (thereby (1.0) providing RWCU more time to restore cheststry Itmits).
- d. When conductivity is within its normal range, then chloride land any other impurittes affecting conductivity) most also (1 0) be within their normal ranges.
i ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 47 8.' ANSWERS -- HATCH 182
-85/03/11-K E BROCKMAN REFERENCE EIH, U1 TS's, 3 4-6 ,
ANSWER 8 20 (0.00) (1.03
- a. (3)
- b. '00000* indicates that there is no Negative Grace Period for I t, would be applicable for Unit 2. (0 5) this survet11 nce.(0.5)
(Since Unit 1 allows plus AND minus OS*.' interval variance) REFERENCE EIH, HNP-ADM-0831 ANSWER G.21 (1.00) d
. REFERENCE . >
EIH, U2 TS'1, 3.5.42 S t a nd in*3 Order $4-35 AflSWER S.0: (1 00) The annuncistor nndow will ba 13b414d with the appropriate ou11ed annonctator control number. 4EFERENCE CIH. HHP-ADM-0903 F
._ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ .______________________________________._____________m_______.____________._____
TEST CROSS PEFERENCE PACE 2 QUESTION VALUE REFERENCE 07 02 1 50 KEB0000017 07.03 1.00 NEB 0000018 07.04 1.00 KEB0000019 07 05 .50 KE80000020 07.06 1 00 KE00000021 07.07 1 00 kEB0000022 07.08 1.00 MEB0000023 07 09 1 00 KEB0000024 07.10 1.00 ME00000025 07.11 1 00 KEB0000027 07.12 2.00 KEB0000028 07.13 1.00 MEB0000029 07.14 2.00 KE00000057 07.15 1 00 KEB0000050 07.16 1 00 KEB0000050 07.17 L.00 MEB0000101 07.18 .50 KEB0000102 OP.19 1.50 MEB0000103 , 07.20 1.00 PEB0000104 07.21 1.00 KEB0000105 07.22 1.00 MEB0000106 ,. 07.23 1 00 KEB0000134 07 24 1 00 MEB0000144 07 25 1 00 KEB0000145 07.26 1 00 kEB0000146 0*.27 1.00 KEB0000147 M.00 08 01 1 00 MEB0000001 06.02 t.00 VC50000002 08 03 .50 VEB0000003 00 04 1 00 VE80000004 08.05 1.50 KEB0000005 00 04 3.00 KEB0000000 08.07 1.00 MEB0000000 00.00 1.00 KEB0000010 00.09 2.00 ME00000011 08.10 1.00 kE8000001 08.11 1 00 LEB0000013 08.t2 1.00 VE80000014 08.13 1 00 KE00000015 08.t8 1 00 KEB0000092 08.15 .50 KEB0000to' 09.14 1 00 KEB0000t40 00.17 1.00 MEB0000100 08.t0 2.50 VEB0000110 08 19 4.00 KEB0000111 08.20 2.00 kEB0000134 09 21 1 00 MEB0000135 08.22 t.00 KE00000148 30.00
~~~~~~
e TEST CROS; REFERENCE PAGE 1 00ESTION VALUE REFERENCE 05.01 1.00 MEB000004: 05.02 1.00 KE00000043 05 03 1.00 MEB0000044 05 04 1.00 KEB0000045 05.05 0.00 MEB0000016 1.50 HEB0000047 , 05 04 05.07 1 00 MEB0000048 05.08 1.00 HEB0000049 05.09 1.00 MEB0000050 05.10 2.50 HEB0000051 05.11 2.50 ME0000005: 05.1 1.00 HEB0000051 05 13 0.00 KE00000054 05 14 1.00 HEB0000055 05.15 .50 MEB0000056 05.16 2.00 tEB0000095 05.17 1.00 NEB 0000096 03 10 0 00 KEB0000097
- 03.19 2.00 KEB0000138 09.20 t.00 FEB000nt30 03.01 0.00 MEB000014' 30 00 06 0t t.00 KEB0000430 06 0 1.00 MEB0000031 M .a 3 1.00 PEB0000010 06 04 1.00 MED0000033 06.0" t.30 HEB0000034 0o.06 1 00 MEB0000?37
'; 6 . 0 ? t.00 LE800000*;6 06.00 0.00 MEB000003' 06.)0 0 00 kEB000101.0 06 10 1 00 MEB0000039 06.lt 1.00 KEE'0000040 00 12 1 00 LEB0000041 04 11 1.00 MEB0000060 06.14 1.00 PCB0000061 04 15 L.00 VEB000004; 04.16 0.00 MEB000006?
04.t* 1 00 FEB0000044 06.10 1.00 FEBoo0000S 04 11 2.00 FEB0000160 06 00 1 00 VEF0000140 06.21 1.00 KEB0000 tat 06.00 2.00 MEB000014: 06.23 1.00 PEE 0000141 30 00 07 01 2.00 KEB00000te
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SYSTEM _ 9-C 3 f j I *-- System Curve D E 5 l -
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I N/M ' Pump 1 Curve 3
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J Flow (Arbitrary Units) SYSTEM HEAD VS F_ Loll PLOT FIGURE FOR 5.05 _ _ _ _ _ _ _ _ . _ . . . - , _ _ . _ _ _ _ _ . , _ _ . . _ . _ _ _ - - - . . _ _ _ . _ _ ______._ __... _____ - ,__..,y ___,_c . _ , _ _ . - _ _ _ , _ _ _ _ . . _ - - _ - _ _ . _ _ - ~ _ _ _ . _ . - , . . _ _ - - .
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GENERAL ELECTRIC COMPANY PROPRIETARY INFORMAT ON. i FIGURE FOR 5.13 r--* - - ' - - ' ~ " " " ' " " ~ ' ~" - _..,,,_..,,__.,_,_._.---e.,
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MCPR LIMIT FOR P8X8R FUEL AT RATED FLOW AND RATED POWER bbMI *b HATCH-2 FIGURE FOR 5.13
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pe. T, tie irwoi ~ - - E. EE6 CIDE _ BEL /Eb_3E6DINQ,QO33EQIl@$_EQ3_16396%_lbEIBLJ%dIjii
- 1. O,h t e i : Orywel! Temperature Reedirig= Tv. iiie 185' Elevat agon.
Taw.perature In:ii ca t o r ET4T R~OO give= ' leas eo. ding for the north e i 1. er.d CT47-RCC1 gires t h .. - i eadirig f or the south l ($ cide. i
. 2. Refer to Figuee 1 an obbin the correcfion fac. tor for each tanperature reading.
3, 4 the correction T ctor- f ound using time North Drywell Temperature Reading f r ew, the level ir.dicetiuri sinown on Level Indi rato r 2021-RE.Ot+A.
- 4. & 4*e correction fac+cr f ciun d ui nig tiie South Drfwell l- Te^p s r sture P+ e ding f run, the level ...u tion sliown on Level
' Iridi rsi o r 2001 FC04D.
C, The at,'brEge of the'b tWs Luftetsew levci r e cs d a rig h will 91Ve
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i e s, \cu. u .pv , ua 9 s (b _w ,,5 L sbom. FIGURE FOR 7.07
L Geo iaPower 7 of 7
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y i retegenee tRll FIGURE FOR 7.07 l
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Unit 11 Plant p> Unit 1 ( ) ( ) , g, g.f y e ,
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STANDING ORDER - NO. 15'(- 3 '/
~
Date Issued //-j2-55A/ Date Deleted ^ TITLE CLARIFICATION OF OPERABILITY APPROVED- W t. / M/*/M n 4 % fl1nvl= Eice GeneraV Manager or Sice "" Manager of Operations, or ' Deputy General Manager Superintendent of Operations ; The following clarification of the definition of operability is now in effect. Any questions concerning interpretation of the below beyond what is explicitly stated in the statement below should be referred to the General Manager or Deputy General Manager. 4 When a system, subsystem, train component, or device having Technical
' Specification operability requirements is determined to be inoperablo solely _because its emergency power source is inoperable, or solely, because its normal power source is inoperable, it may be considered
. operable for the purpose of satisfying *the requirements of its- -
applicable Limiting Condition for Operation, provi de d: (a) its 4 corresponding normal or emergency power source is operable; and (b) all its redundant sys' tem (s), subsystem (s), train (s) component (s) and
, device (s) are operable, or likewise satisfy the requirements of this -
specification. Unless both condition (s). (a) and (b) are satisfied; enter the applicable Limiting Condition for Operation as specified by the Technical Specifications, or the unit .shall'be placed in at c least Hot Shutdown within the next 6 hours, and in at least Cold Shutdown within the following 30 hours. The clarification stated aboy'e is not applicable in Operational
. Conditions for 4 or 5 for. Unit 2,. zed Ovia Shuidu-o e r n f;:' ' g f r L' n ' t b. Af e2 /g 9 U FIGURE 1 HNP-12 R10
_ _ __. _ . ______ _ ____ _ -_. u __ 2_..___. ..
c p-- }
,, 3/4.3.1 RIACTOR PROTEti10N SYSTEM INSTRUM*KTATION l
LIMITIt:C CONDITION FOR OPERATION 1 l 3.3.1' As a minimum, the reactor protection cystem instrumentation channl shown in Table 3.3.1-1 shall be OPERAELE with theare REACT Set points and interlocks. RESPON!! TIME as shown in Table 3.3.1-2. given in Table 2.2.1-1. .
. .' APPL:CASILITY: As shown in Table 3.3.1-1. sp- l l
ACTIOM: l
- a. liith the reouirements for the minimum number of OPERABLE c satisfied for one trip system, place at least one inoperable channel in the tripped condition within one hour.
u b. 1.'ith the requirenents for the minimum n' mber of OPERASLE channels not satisfied for both trip systems, place at least cne inoperable channel in at least one trip system
- in the tripped condition within one hour and take the ACT201: required by Table 3.3.1-1.
l
- c. The provisions of Specification 3.0.3 are not applicable in OPERA-TiONAL C0tjDIT10N 5.
- SUR'.*Ii.LL Ar!CE REOU1 RIP.If;TS .
i l I
-if coin enannels are Tric k inoperable in ene trip syst Function te oc:ur.
exct-t when tnis co.it cause the A. .cnd cr.t ::c,. E 3/4 3-1 Hai t.-: - Ut:IT 2
-a
I .. 9 1 TAHi.E 3.3.1-1 ItEACTOR PROTECTION SYSTEH INSTRilHENTATION APPLICADU4 HININUM NUMBER - OPER.WIONAL OPERARLE CilANNELS
- h. FilNCTIONAL tlNIT - -
' CONI)lTIONS ' PER TRIP SYSTEN(a) ACT100f 0 /. 1. Intermediate Range Honitors: . , d (2C51-K601, A, B, C,I), E, F, G, H)
- 1 H ,
' " a. Neutron Flux - High 2 * , 5( } ' 3 1 - 13 Inoperative 3, 2,5 g) 2 2 3 I t 3,4 2 2
- 2. Average Power Range Honitor:
(2C51-K605 A, B, C, D,'E, F) .
- a. Neutron Flux - Upscale, 15% '
2, 5 2 - I
- h. Flow Referenced Siinulated
- Thermal Power - lipscale 1 2 3
, c. Fixed Neutron Flux -
L Upscale, 118% 1 2 3 , d. Inoperative 1, 2, 5 2 4
- e. Downscale. 1 2 3
- f. I.PRil 1, 2, 5 -
(d) NA L 3. Reactor Vessel Steam Dome Pressure - j liigh (2fl21-N678 A, II, C, D) I, 2(e) 2(J, 2B21-N045. 5 A, B, C, D) l ! g . . g 4. Reactor Vessel Water Level - I.ow (Level 3) (2821-N680 A, B, C, D) 1, 2 2(j' 2821-N681 A, B, C, D) ! 5 , l g-
- 5. flain Steam Line Isolation Valve - g) w Closure (NA) 1 4 3
- 6. ifain Steam Line Radiation - High 1, 2(e)' -
6 O (2DII-K603 A, R, C, D)
- 7. Drywell I'ressure - High 1, 2 I8) 2 5 .
(2C71-N650 A, B, C, D) .
.0
~
TAptE 3.1.1-1 (s'aust launcd) lifiAC10R PH011CrlON fiYffilM litil14tM3frATION a Al'11.l(*Allt E NINIMM MMER (Mt'llATII HAI. (Mt34AlltE OtAMe'.lS F13Crf009d,(MIT (11NillTit eti ACFWNI i g 5434 lit [P SY9ttM(a) _ 8 Scram Discharge Volimme unter -
.e la Imvel - liigh (2 Cal-lill3A,II,C,0) 1, 2, '. (h) 2 4 -
tevel - Illgh (2Cll-N060A,II,C,il) 1, 2, 5 2 4l
- 9. Turblne Stop valve - Cloeute (NA) 1(II 4 (k) y
- 10. 1brhine Onntrol Valve Fast Closure, Trlp Oil Pressure - Isne l(I) 2(k) 7 (2C71-N005A,B,C,D) .
i -
- 11. neactor Mxte switdi in slie
- telown Posit!cn (NR) 1, 2, 3, 4, 5 1 8
- 12. Manual Scran (NA) 1,2,3,4,5 1 9 O
I J 3 y
't
~
a o k e e g
9 i '. , n . , ,J - TA8LE 3.3.1-1 (Continuedi REACTOR PROTTCTION 5? STEM INSTRUMENTATION ACTION . ACTION 1 - In OPERAT!0NAL CONDITION 2. be in at least HDT SHUTDOWN within 6 hours. l In OPERATIONAL CONDITION 5. suspend all operations involving CORE ALTERATIONS or postive reactivity changes and fully insert all insertable control rods within one hour. ACTION 2 - Lock the reactor mode switch in the Shutdown position within one hour. - ACTION 3 - Be in at least STARTUP within 2 hours.
- l ACTION 4 - In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN .
within 6 hours. l. In OPERATIONAL CONDITION 5, susoend all operations involving 1-CORE ALTERAT!CNS or positive reactivity changes and fully 4 insert all insertable centrol rocs within one hour. l 1 ACTION 5 - Be in at leist HOT SHLTDOWN,within 6 hours. , ACTION 6 - "Be in STARTUP with the main stear. line isolation va'1ves closed withia 2 hours or in at least HOT SHUTDOWN within 6 hours. [ ACTION 7 - Initiate a reduction in THERMAL POWER within 15 minutes and be at less than 30t of RATED THEP.E POWER within 2 hours. ACTION 8 - In OPEMTIONAL CONDITION 1 or 2, be in at least _ HOT SHUTDOWN within 6 hours. l In OPEMTIONAL CONDITION 3 or 4, irrne:iiately and at least once per 12 hours verify tnat all control rods are fully inserted. ' In OPEMTIONAL CONDITION 5, suspend all operations involving CORE ALTEMTIONS or positive reactivity changes and fully insert all insertable control rods within one hour. 4 Amendment No. 8 i HATCH - UNIT 2 3/4 3-4
~ ' ' TABLE 3.3.1-1 (Continued) ,
' fEACTOR PR3TECTION SYSTEM INSTR &ENTATION ACTION 9 -' In CPERATIONAL CorcITION 1 or 2, be in at least PCT SMUT 00WN e within 6 hours.
~
In OPERATIONAL CONDITION 3 or A, lock the reactor mode switch in the Shutdown position within one hour. In OPERATIONAL CD' CIT]DN 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour. TABLE N3TATIONS
- a. A channel maf De placed in an inoperable status for up to 2 hours for required surveillance without pla:Ing the trip sy stem in the tripped condition provided at least one OPERABLE channel in the same trip system ,
is monitoring that parameter.
- b. The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accorcance with Specification 3.10.3.
- c. 'The IRM s:rans are automatically bypassed when the reactor vessel mode switch is in the Run position and all APRM channels are OPERASLE and on scale.
' d. . An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.
- e. These functions are not required to be OPERASLE when the rea: tor pressure vessel head is unbolted or removec. i f.
This function is automatically bypassed when the reactor mooe switch is in other than the Ran position. - g. This fuvtion is not reagired to be OPE *ABLE when PRIMRY CONTA:tfEry T j
- INTEGo.lTY is not reo.rireo; this function may be typassed when ne:essary t t
for contaimient inerting or c'e-inerting (purging). ) l
- h. With a7y control rod withdrawn. Not applicable to control ' rods removed I per Spe:ification 3.9.11.1 or 3.9.11.2. \
7
- 1. These fuTtions are bypassed when turbine first stage pressure is $253*
I 4 psig, equivalent to THER4L P0 AIR less than 3CN of RATED T4kAL P0nIR J. Also trips reactor coclant system recirculation pump MG sets. ,
' k. Also trips rea: tor coolant system recirculation pump motors. ,
- Initial set;,; int.
Final setpcint to be determined durirg stdrtup testing. Amendment No, p. 29 HATCH - LNIT 2 3/4 3 5 4
~'~ ~
" -- - w , _
,e,ee- ywW g --vm--u--mwe--r-p--er ,y ww- -+7p- -*r'--'-ev-M -w'=-*-'N -W W e+ eiw 4 -w,e+-ver- g - ----y- y- rw- T--------Wn-* C-e
. INSTRUP.ENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION . 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the
. values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.
APPLICABILITY: As shown in Table 3.3.2-1. ACTION:
- a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition
- until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place at least one inoperable o channel in the tripped condition
- within one hour.
9
. c. With the requiremen'ts for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoper-able channel in at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.
- d. The provisions of Specification 3.0.3 are not applicable in
. OPERATIONAL CONDITION 5.
SURVEILLANCE REQUIREMENTS I
- Witn a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTICN required by Tarle 3.3.2-1 for that Trip Function shall be taken.
"If ficth channels are inrDcrable in one trip syster., select at least one inoperabic channel in that trip system to place in the tripped condition, except when that would cause the Trip Function to occur. 'l HATCH - UNIT 2 3/4 3-9 Amendment No. 8
~ ,, - __
, w i
. . _ . . __ _ . _ . . + - .
_ _ _ . _ . . _ _ _ _ _ _ . - . , _ _ _ m_. . . .. _ _ _. TARI.E . .2-1 . . ISOI.ATION ACTUATION INSTRitIENTATION ' l l g VALVE GROUPS HINIHitl NUMBER APPLICARLE
*s OPERATED BY OPERARI.E CilANNELS OPERATIO11AL h }Hil*{llNCTION SIGNAI.(a) PER TRIP SYSTEN(b)(c) CONDITI0ff ACTIGH I. PRINARY CONTAINtfENT IS01.AT1018
- a. Reactor Vessel Water Level :
I
- 1. Low (Level 3) -
2, 6, 10, 2' , 1, 2, 3 20 ? 3 (2821-N680 A, B, C, D) 11, 12
- 2. Low-I.ow (Level 2) 5, f,
- 2 1, 2, 3 20
- (2R21-N682 A, B, C, D)
- 3. Low-Low-I.ow (Level 1) 1 2 -
I, 2, 3 20 (2821-N681 A, B, C, D) -
- h. Drywell Pressure - Nigh 2, 6, 7, 10, 2 1, 2, 3 , 20 (2C71-N650 A, B, C, D) 12, f,
- l 4 .
I w c. Main Steam Line i D 1. Radiation - liigh 1, 12, f, (d) 2 1, 2, 3 21 l u (2Dil-K603 A, B, C, D) { l ..
~
2.* Pressure - Lo.a 1 2 1 22 1 j (2R21-N015 A, B, C, D) 1 3. Flow - liigh 1, # 2/line 1, 2, 3 21 ) (2B21-N6P6 A, R, C, D) - i (2il21-N687 A, B, C, D) ! (2821-N688 A, R, C, D) 1 (2B21-N689 A, B, C, D) ,
- d. Main Steam Line Tunnel .-
h Temperature - liigli 1 2/line
- 1, 2, 3 21
) g (2R21-N623 A, B, C, D)
) g (2B21-N624 A, B, C, D) ,
l g (2821-N625 A R, C, D) { <+ (2H21-N626 A, B, C, D)
- e. Condenser Vacuum - Low I 2 1, 2 ,3 23 g (2B21-N056 A, B, C, D) e 1
g f. Turleine Building Area
; Temperature.- liigh 1 2(,) 1, 2, 3 21 (21161-R001, 2U61-R002, 2U61-R003, , ,
2tl61-R004) '
TARI.E 3.3.2-1 (Con t i nucil) ' ISOI. Air 10N ACTilATION INSTRIRIENTATION , f VAT.VE CRot>PS HINIMIM NIMBTR APPLICABLE
*A -
OPERATED llY OPERARI.E CllANNELS OPERAT1011AL
*? Tl!IP FilNCTION SIGNAI.(a) PER TPIP SYSTEM (b)(c) CONDITMN ACTIott U
l 2. SECONilARY CONTAINNENT ISOI.ATION . s l a. Reactor Building Exhaust Railiation - liian 6, la, 12,
- 2 1,2,3,5 and** 24
; (2 fill-K609 A, D, C, D) l- Drywell Pressure - Higli 2, 6, 7, 10, 2 1, 2, 3 24 (2C11-N650 A, B, C, D) 12, f, *
- c. Reactor Vessel Water I.evel - I.ow I.ow (i.evel 2) 5, f ,
- 2' 1, 2, 3 24 (2D21-N682 A, 8, C, D) '
' h al . Refueling Floor Exhaust Y Railiation - liigh , 6, 10, 12, f,
- 2 1,2,},5 and** 24 C (2Dil-K611 A, B, C, D) .
i
- 3. REACTOR WATER Cf.EAtluP SYSTEtt ISol.ATION
~
{ .a . A Flow - liigh (2G31-N603 A, R) 5 1 1, 2, 3 25
- h. Area Temperatiire - High 5 1 1,2,3 25 (2G31-N662 A, D, E, 11, J, H) l .
3 c. Area Ventilation A Temp. - High 5 1 1, 2, 3 25 R (2G31-N663 A, D, E. H J, H; . R 2G31 -N661 A , 11, E , 11, J , H ; 2G11-N662 A D, E,11, J. H) l z d. SI.CS Initiation (NA) 5(g) NA 1, 2, 3 25
; P '
w
- c. Re a r t a r Ve s s e l Wa t e r f.evel - I.ow I.aw 5, 7,
- 2, 1, 2, 3 25 (l.cvel 2) (2B21-N682 A, B, C, II) ,
P e
TARI.E 3.3.2-1 (Continueri) '
' ISOI.ATION ACTIIATION INSTRlRIENTATION f
a 9 ' VALVE GRollPS 4 MINIMllH Nitf8ER APPLICABLE h s TRIP FtlNCTION OPERATED BY OPERARLE CllANNELS OPERATIGIIAL . 3 -- SIGNAI.(a) PER TRIP SYSTEH(Is)(cl CONDIT15
- ACTI0lt
- 4. 111 011 PRESSIIRE COOLANT INJECTION SYSTEH ISOLATION a, llPCI Steam Line Flow - liigh 3 1 1, 2, 3 26 (2E41-N657 A,5). t l i
, b. IIPCI Steam Supply Pressure -
- l I.ow (2E41-N658 A,B,C,D) 3,8 2 26 l
1, 2, 3 l ,
- c. HPCI Tiirbine S haust Diaphragm !
Pressure a rk (2E41-N655 A,B,C,D) 3
" 2, 1, 2, 3 26 l i *
*- d. HPCI N;e iv.stration Room j u Te n;-r : etm c flish (2E41-N671 A, 8) 3 -
1 1, 2, 3 26
! C l
, e. Suppres u na Pool area Ambient
- Temg.e e t ' re - b i g t. (2E51-N666 C, D) 3 1 1, 2, 3 26 j f. Suppression Pool Area '
A Temp.-liigh (2E51-N665 C, D; 3 1 1, 2, 3 26
! 2E51-N663 C, D; i
2E51-N664 C, D) i
'y g. Suppression Pool Area Temperature j % Timer Relays (2E41-H603 A, R) 3(g) 1, 2, 3 26
;' it 1
@ h. Emergency Area Cooler Temperature- .
) 11igh (2E4I-N670 A, R) 3 l E 1 1,2,3 26 l
- 1. Drywell Pressure-High * *
? (2 Ell-N694 C, D) -
8 1,* 2, 3 l$ 1 26 J. Logic Power Honitor (2E41-K1) NA II'}
, I 1, 2, 3 27
.. t 3
TARI.E 3.3.2-1 gt:caticued) TSOf.ATION ACTilATION INSTRINIRNTATION - VAI.VE CROllPS HINIMIRf NilHRER APPI.ICARIE. OpF. RATED BY OPERARI.E CNANNELS ic TRIP FilNCTION OPERATIONAL
- 5. SIGNAL.(a) PER TRIP SYSTEH(h)(c) CONDITIGy_ ACTIGH REACTOR CORE ISol.ATION _
C001.ING SYSTEH ISOI.ATION ' k, j 7j a. RCIC Steam I.ine Flow-High m (2E51-N657 A,5) 4 1 i,2,'3' 26 l b. i RCIC Steam Supply Pressure - I.ow (2E51-N658 A, R, C, D) 4, 9 2 1, 2, 3 26 l
- c. RCIC Turbine Exhaust.
Diaphragm Pressure - High 4' 2 (2E51-N685 A, B, C, D) 1, 2, 3 26 g it. Emergency Area Cooler Temperature - . 5-liigh (2E51-N661 A, R) 4 I y . 1, 2, 3 26
,, c. Suppression Pool Area Ambient Temperature-High 4
! *(2E51-N666 A, R) - 1 1, 2, 3 26
- l
- f. Suppression Pool Area a T-Nigh 4 1 (2E51-N665 A, B; 2E51-N663 A,R;
, 1, 2, 3 26 2E51-N664 A,5)
Suppression Pool Area Temperature g. Timer Relays (2E51-H602 A, R) 4(g) 1
, 1, 2, 3 26
- h. DrywcIl Pressure - Nigh p
E y i. (2E11-N694 A, R) I.ogic Power Honitor (2E51-XI) 9 NA(h) 1 1, 2, 3 26 l,! 1 1, 2, 3
$ 27
- 6. SHilTDOWN C00l.ING SYSTEM ISOI.ATION
- a. Reactor Vessel Water Level-Low (Levell 6,.10, 11, 2
." 3)(2R21-N680 A, R C,11) 12 2 3,4,5 26 W .
- b. Reactor Steam Dome Pressure-High 11 1 1, 2, 3
) (2R31-N679 A, D) 2R
T9104 3.3.2-1 (Centirund) ISOLATION ACTUATION INSTRL*tE.VTATION ACTION ACTION 20 -- Be in at least HOT SHUTDOVN within 6 hours and in COLD SHUTDOWN within the next 30 hours. ACTION 21 '- Be in at least STARTUP with the main steam line isolation valves closed within 2 hours or be in at least NOT SHUTDOWN within 6 hours and in COLD SHUTDOWN within the next 30 hours. ACTION 22 - Be in at least STARTUP within-2 hours. ' C
. ACTION 23 -
Be in at least STARTUP with the Group 1 isolation valves closed within 2 hours or in at least HOT SHUTDOWN within 6 hours. ACTION 24 - V Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within one hour.
, ACTION 25 -
Isolate the reactor water cleanup system. ACTION 26 - Close the affected system isolation valves and declare the affected system inoperable. ACTION 27 - Verify power availability to the bus at least once per 12 hours or close the affected system isolation valves and declare the affected system inoperable. ACTION 28 - Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam done pressure $ 145 psig. l NOTES
# Actuates operation ~of the main control room environmental control system in the pressurization mode of operation.
Actuates the standby gas treatment system. When handling irradiated fuel in the secondary containment. a. See Specification 3.6.3, Table 3.6.3-1 for valves in each valve group.
- b. A channel may be placed in an inoperable status for up to 2 hours for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter. '
c. With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within .2 hours or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken. , d. Trips the mechanical vacuum pumps.
- e. .
A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.
- f. May be bypassed with all turbine stop valves closed. I
- g. Closes only RWCU outlet isolatica valve 2G31-F004
- h. Alarm only.
- i. Adjustable up to 60 minutes.
KATCN - UNIT 2 3/4 3-15 Amendment No. 9, 39
', 3/4.5 MP.GD'OY CP"" COOLI!:S ?.'l!Ti~i5
?/4.5.1' HICH l'n~5SURE C00Ud!T I :K.C110'595TG1 J.Iit!TI"G CO::01T10:[POR O_?f?.ATION ..
.r .
3.5.1 The High Prassure Coolcnt Injection (IIPCI) system 's'hal'1 ti * ( ' OPEPhl:LC uith: .. . . .
- a. One OPEidELE higti pressure cool:nt injection pump, and . .
- b. An OPEPAULE flew p:th capable of taking suction frem the suppression chmber and transferring the wster to the reactor -
pressure vessel. ' **
; 'l APPL 7Cf.BILIYY: CONDITIONS 1*. 2* and 3* with resctor vessel staam dome pressure s 150 psig. ,
ACTION: ~ With the HPCI system inoperable, P0k'EPw OPEPATION may continue a. and the provisions of 3.0.4 do not apply *, provided the RCIC system, ADS, CSS and LPCI system are OPERABLE; restore the inoperable HPCI system to OPEPABLE status within 14 days or
- be in at least HOT SHUT 00WN within the next 12 hours and reduce reactor steau deme pressure to 1 150 psig within the*
- following 24 hours. ..
b., With the rurveillcnce re;uirements of Specification 4.5.1 not perfemed at the requirts frequencies due to low reactor steam pressure, the provisions of Specificcticn 4.0.4 are not applic-able provided the appropritte surveillance is performad within 12 hours after reactor stccm pressure is adequate to perfom the tests.
- c. In tho' cvont the HPCI is actuctcc and injects water into the reactor coolant system, c Special Rep;rt shall be prepared and -
- submitted to the Ccani sica pursu:nt to Spacific: tion o.9.2 within 90 days descri'oing the circumstances of the actention and the total accumulated actuations cycles to date.
-SURVEII.LARCE REOUIP.D1ENTS '
t l l 1 "
- ice Special lest Exception 3.10.5 3/4 5-1 t.mendm:nt No.10 HATCil - U!i1T 2
., . . L _.,....
- y'
~, ,,g r- - - - c - - - - -, .----,
Y -
EMERGENCY C0'E COOLING SYSTEMS , 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM LIMITING CONDITION FOR OPERATION ak[ 3.5.2 The Automatic Depressurization System'(ADS) shall.be OPERABLE with at least seven OPERABLE ADS valves. APPLICABILITY: CONDITIONS 1, 2 and 3 with reactor vessel steam deme pressure >l50 psig. ACTION:
~
- a. With one of the above required ADS valves inoperable. PCWER OPERATION may continue provided the HPCI, CSS and LPCI systems are OPERABLE; restore the inoperable ADS valve to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 nours and reduce reactor vessel steam dome pressure to 1 150 psig within the following 24 hours.
- b. .With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam dome pressure to 1 150 psig within the next 24 hours,
- c. With the Surveillance Requirement of Specification 4.5.2.b not perfomed at the required interval due to low reacter steam pressure, the provisions of Specification 4.0.4 are not applicable provided the appropriate surveillance is perfomed within 12 hours after reactor steam pressure is adequate to perfom the tests. .
SURVEILLANCE REQUIREMENTS HATCH - UNIT 2 3/4 5-3 t
EMERGEN(.Y LUNi t.vut 4 nu a w e u y . 3/f 5.3 LOW EESS'r_;g 797g 3t3g3 gvg7gog CORE SPRAY SYSTEM , I'.D*.: TING COND: TION FOR OPERAT!DN 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:
- a. One OPERABLE CSS pump, and
- b. An OPERABLE flow path capable of taking suction frot at least one of the following OPERABLE sources and trar.sferring the water through the spray sparger to the reactor vessel;
- 1. In CONDITION 1, 2 or 3. from the suppression pool.
- 2. In CONDITION 4 or 5*;
- a) From the suppression pool, or
'b) When the suppression pool is being drained, from the condensate storage tank containing at least (150,000) gallons of water.
APPLICABILITY: CONDITIONS 1, 2, 3, 4, and 5*. ACTION:
- a. In CONDITION 1, 2 or 3;
- 1. With one CSS subsystem inoperable, POWER OPERA ION may continue provided both LPCI subsystems are OPEPABLE;
- restore the inoperable CSS subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOW't within the next 12 hours and .in COLD SHUTDOW?i within the following 24 hours.
- 2. With both CSS subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within th next 24 hours.
- 3. In the event the CSS is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 v.ithin 90 days describ'ng -he cir-cuestances of the a::uation and tr.e tc al ac:u f a se a.ctuation cycles t: Cate.
3 e r.: rs:.i se :
- Ine core spray sys s. anc tne s;- ression cnar:er an: t7e be OPERABLE proviced that the reactor vessel head 15 re ove:
cavity is flooded, the spent fuel pool gates are re ove:, a d t e , water level is raintained withir. tne. limits of Specific 1 tic s 3.3.3 and 3.9.10 3/4 5-4 Amendesnt *,3. 6 M *.7-u . om7 7 -- -
lEME*.?!f:CY CORF C00L?'a3 !YSTEMS . LIMITING CONDITION FOR OPERATION (Continued)
't .
ACTION'(Continued) .' . b.~ In CONDITION 4 or 5*; .
- 1. With one CSS subsystem inoperable, operation may continue provided that at least one LPCI subsystem is OPERABLE within '4 hours; otherwise, suspend all operations that have a potential for draining the reactor vessel.
- 2. With both CSS subsystems inoperable, operation may <
continue provided that at least one LPCI subsystem is
- OPERABLE and both LPCI subsystems are OPERABLE within 4 hours. Otherwise, suspend all operations that have a potential for draining the reactor vessel and verify that at least one LPCI subsystem is OPERABLE within 4 hours.
- 3. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS t i l l 1 l 0 3/4 5-5 Amendment No. 6 l HATCH - UNIT 2 l l
\
4
EIERGENCY CORE COOLING, SYSTEMS, E LOW PRESSURE COOLANT INJEC. TION SYSTEM b LIMITING CONDITION FOR OPERATION 3.5.3.2 Two independent Low Pressure Coolant Injection (LPCI) sub-systems of the residual heat removal system (RHR) shall be OPERABLE with each subsystem comprised of:
- a. Two OPERABLE RHR pumps,
- b. An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water to the reactor pressure vessel.
APPLICABILITY: CONDITIONS 1, 2, 3, 4* and 5*, **. ACTION:
- a. In CONDITION 1, 2 or 3;
- 1. With one LPCI subsystem or one LPCI pump inoperable, POWER OPERATION may continue provided both CSS subsystems are OPERABLE; restore the inoperable LPCI subsystem or pump to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SRUT-DOWN within the following 24 hours.
T
- 2. With both LPCI subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours and either be in COLD SHUTDOWN or maintain reactor coolant temperature < 400*F by use of alternate heat removal methods within the following 24 hours.
- 3. With the LPCI system cross-tie valve open or power not removed from the valve operator, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the following 24 hours.
- 4. In the event the LPCI system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated acteation cycles to date. .
- b. In CONDITION 4* or 5*, ** with one or more LPCI subsystems inoperable, take the ACTION required by Specification 3.5.3.1.
The provisions of Specification 3.0.3 are not applicable.
- Not applicable when two CSS subt.ysta.is are OPERABLE per Specification 3.5.3.1.
**Not applicable when the (.55 is not required to be OPERABLE per P Specification 3.5.3.1.
HATCH - UNIT 2 3/4 5-1 4
,. 3/4.9.4 !UPPWSSION CHA'W
- LIMITING CON 01 TION FOR OPERATION 3.5.4_ The suppression charter shal1 be OPERABLE with a minimum 653,000 gallons, ec;uivalent to a level conta5eed water volume of of 12'8" and the water level instrumentation 12'2" except channels that the alarms adjusted suppression to actuste at a low water level 1 4
' chamber may be drained: .
- a. In OPERATIONAL CONDITION 4, provided that;
- 1. No work is performed which has a potential for .
draining the reactor vessel,
- 2. The reactor m:de switch is locked in the Shutdowr.
position, and
- 3. The core spray system is 0PERASLE per Specification 3.5.3.1 with an OPERABLE flow cath capable of taking 4
' suction from the OPERA 5LE condensate storage tank and transferring the water through the spray sparger to the
' reactor vessel.
b. In OPERATIONAL CONDITION 5, provided that the reac switch is locked in the Refuel position, and:
- 1. The core spray system is GPERA5LE per Soecification 3.5.3.1 with an OPERABLE flow path caoable of takino suction from the OPERA 3LE condensate storage tank ar.d transferring tne water through the spray sparger to the reactor vessel, or
- 2. The reactor vessel head is rer:oved and the cavity is ficoded, tne spent fuel cool gates are removed, ar.d the water level is maintained within the limits cf Specifica- l tions 3. 9. 3 snd 3.g.10 . ,
' APPLICASILITY:
C0iiDITION 1, 2, 3, 4 and S. ACTICit:_
- a. In CO*;DIT!01: 1, 2 or 3 with the sue:ression cham:er water level less than tne above limi , restore tne water level to within the limit within 1 hour or be in at least HOT SHUTD0'.-l within the next 12 hours and in COLD SHUTCEf! within the following 24 hours.
- b. In C0t DITIOtt 4 or 5 with the su;;oression cha..ber drained and the conditions of Specification 3.5.4.a or 3.5.4.b, as -
4 apslicable, not satisfied, suspend all oserations in the react:r vessel and all positive reactivity enanges. The provisiens cf Scecificatien 3.0.3 are not a;sticatie. Amendment No. f, 25 Mt. CH - U:.IT 2 , 3/*59
EME?.IEN;Y COT.! CC3'.:f;G S"!TIMS LIMITIGS CONDITION FOR OPERATION (Continued) ACTION (Continued) ,
- c. With one suppression chamber water level instrumentation channel inoperable, restore the inoperable ' channel to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the 4
next 12 hours and in COLD SHUTDOWN within the following 24 hours and verify the suppression chamber water level to be > 12'2" , at least once per 12 hours.
- d. With both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel to OPERABLE status within 6 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours and verify the suppression chamber water level to be 3; 12'2" at least once per hour.
SURVEILLAN'CE REQUIREMENTS l 3/4 5-10 Amendment N:. 6 HATCH - UNIT 2
- ~ - , n, - , -- , - - - - - - - - - - - - - - , - - - , - - , , . . , . . - - - . . - , , . - . --,.,--------,.---.----------..,L. .L . - , - ~ . . . - - , - _ . . - . - . - , - -
, - CONTAINMENT SYSTEMS 1
PRIMARY CONTAINMENT HYDROGEN RECOMBINER SYSTEMS
~
s l LIMITING CONDITION FOR OPERATION ) l 3.6.6.2 Two independent primary containment hydrogen recombiner systems i shall be OPERABLE. APPLICABILITY: CONDITIONS I and 2. ACTION
- a. With one hydrogen recombiner system inoperable, restore the inoper-able system to OPERABLE status within 30 days or be in at least NOT SHUTDOWN within the next 12 hours. The provisions of Specification 3.0.4 are not applicable.
- b. With both hydrogen recombiner systems inoperable, be in at least HOT SHUTDOWN within 12 hours.
SURVEILLANCE REQUIREMENTS
/
3 e 0 I
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l l l 1 UNIT 2 3/4 6-43
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$$ Se 12 93 62 93 112 93 162 93 21293 312 93 412 93 Silt) 612 93 712 93 81293 912 H G81 G7 = 0 01733 7 946 8 546 9IM 9 702 10 267 il 36 a IF 48% B3 $43 le 677 15 769 16 859 17 94r n 2S6 43 III2 9 1204 9 1234 2 1259 8 1283 6 1332 6 1381 8 1431 S 1482 0 IS33 3 1585 5 163s
- s 0 41 % i H01 1 6933 1 7237 5 7518 I Usl I 82 % I 8710 l 9121 8 9307 I 987 2 022 2 bti te Sh 1 29 5729 10729 157 29 20729 30729 40729 $07 29 60729 707 29 80729 90723 0927!? e 0 01730 7 174 7M7 7 415 8 354 8 881 9 400 to 45 II 438 12 446 Il 450 14462 15 452 16 45 h 262 21 11N 6 Ilt! 6 1200 0 1233 5 1258 $ 1283 2 1332 3 1381 S 1431 3 1481 8 1533 2 1585 3 1638 4 s 0 4273 1 6440 1 6492 14934 I 7134 1 1417 I 7681 1 8168 1 0612 I 9024 1 9410 89D4 2 0120 2 0450 Sh 2 02 S2 02 10202 1$2 02 20202 302 02 40202 502 02 402 02 702 02 80202 902 02 88 , 0 01743 6 633 6 675 7 195 7 697 8 106 SH7 9 61$ 10 $$2 18 484 42 412 13 3D 14 M1 15 183 097988 h M163 1179 8 1180 3 12070 1232 7 12579 1782 7 1331 9 1341 3 1431 8 1441 6 11330 IS45 2 1638 3 s e 4344 5 6375 1 6390 1 6731 1 1040 1 7324 I M90 1 8077 I 0522 1 0035 I 9321 1 9645 2 0031 2 036!
Sh 4707 9707 147 07 19707 29707 39707 49707 MF 817 697 07 79707 09707 39 e 0 01748 6 205 4 664 7 133 7590 8 039 8922 9 793 10 6M 11 122 - 12 382 13 240 14 097 (302 13) h 272 74 8100 6 1206 0 1232 0 1257 3 1282 2 1331 6 1381 0 1430 9 1481 5 1532 9 1585 1 1638 2 s 0 4411 1 6316 8 # 40 1 69S1 1 F237 I not t 1993 I salt i NS2 1 9238 i H03 8 9949 2 0219 Sh 4239 92 39 142 39 192 39 292 39 392 39 492 39 M2 39 692 39 79239 892 M 75 e 8 03753 $ 814 6 204 6 645 7 074 7 494 8 320 9 135 9 945 10 M0 11 553 12 35S 13 165 (307 6il n 2H M 1881 9 1205 0 1231 2 12$6 7 1281 7 1331 3 1380 7 1430 F 1481 3 IS32 7 1583 0 1638 i s 0 4474 1 6260 1 6554 1 6068 1 71 % 1 7424 1 7115 18Mt 1 8774 1 9161 8.95M IM72 2 02C2 Sh = superheat. F h = enthalpy. Stu per Ib y = specibe volume. cu it per Ib s = entropy, Stu per F per Ib w 1 ff
- MR
V - ., 0 ,
- g h Telple 3. Superfleeted Steam-Continew -
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@d. Sh 33 74 83 74 In 74 143 74 733 74 283 74 383 74 4f174 583 74 48374 783 74 083 74 983 74 1983 74
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e 9 01767 5167 5445 5 040 6 773 6 $97 6tu 7 330 80S7 s 768 9 400 to its le ett il att i2 310 13 014 8886288 h 206 S2 Il04 2 1203 0 12M 7 IMS$ 1780 8 1305 4 13306 lam ? 1430 3 1441 0 1132 4 1604 7 1637 9 1991 9 1746 8 s $4590 1 6159 163% 16746 1 7908 1 7279 1 7532 4 7772 187M 1904 1 9021 1 9306 8 9733 2 0063 2 8379 2 0687 54 79 77 79 77 Ill ?? I79 77 229 ?? 279 77 379 77 47*, 77 579 1 [ 679 77 771 77 g79 77 979 77 1019 h a = 0 017 % 4 895 5 178 5 50S 5 069 6 773 6 SP2 6 917 7 600 0 777 8 950 9 621 10290 19 958 IllM ' 12 790 1370 281 e 790 *9 1185 3 1707 0 1278 9 1754 9 1780 3 130$ 4 1330 7 1380 0 1430 8 . 1480 8 IS32 3 8604 6 1637 4 1691 4 174 7 s 0 4643 1 6I13 1 6323 luu 16940 1 7217 4747 I Fill 1 81 % 1 8570 -1 8957 19H3 19H9 7 0000 7 0316 7 0619 SA M SF 75 87 t/SS7 17507 !?S 87 / 5 47 Jh48 45 87 ' [7507 6b 8) ' 7& n 7 844? 97587 107s ar 95 e 0 01770 4 651 4 84$ S 20s S %I 5 889 6 771 6 See 71% 7838 8 477 0111 9 747 191ao 18 017 11 64 . 1324 135 a 294 70 1186 7 1700 9 1728 1 1754 3 1779 8 130S 0 11;9% 11 9s 7 14?9 9 Idem IS32 8 suaS 1637 1 1691 7 174t s s 0494 160b9 1 6753 8 6540 16676 I 7149 I 7404 1 164S I 8044 I 850* I 4W l 926/ I 9605 I 9940 70?% 7cm . Sh 27t8 77 18 122 le 172la ???II ??? 18 377 18 47218 572 18 67219 77718 87718 97718 107718 les -e 0 01774 4 all 4 $90 4 935 S7% 5 $48 $ 904 6 Fil 6 43J 7 44i 8 050 86% 9 248 9 abo 10 40 il0% 1327 87 n 29s 54 11077 1899 9 1727 4 12S3 7 1279 3 1304 6 1379 6 1379 5 1829 7 las 4 1532 0 ISee 4 IMF6 16986 1746 S e 047a3 8 6027 I 6187 I Hll I 6814 1 7084 IFM4 3 7306 8 80J6 I S4SI l 8839 I 9205 1 951' I 9083 2 0199 2 0S02 Sn 1863 6863 188 63 164 63 21863 26463 36863 46863 % 863 664 63 764 63 MN3 968 63 1064 63 ist e 0 01778 4 731 43S9 4 690 5 007 5 315 5 617 5 915 6 SO4 7 006 jus 8 241 0 816 4 119 9 969 19 537 13313h h 307 24 1880 0 t1988 17M 6 1753 1 !??B 8 1304 7 1329 7 1379 7 1829 4 1480 3 IS318 1584 7 16b S 1696 S 1746 4 s 0 4790 ISMS I 6127 1 64 % 86755 1 7031 1 7288 8 1530 1 7981 1 8396 8 8785 i SISI I 9498 8 9828 2 0l4) ' 2 0448 Sh 15 23 ES 21 115 21 46S 21 715 21 26S 21 36S 71 465 21 MS 23 6ti28PM i abs 71 96$ 21 1065 71 lie e 0 01787 4 048 4 349 4 #8 4 777 5 068 5 357 5 647 6 20$ 4 761 7 334 7 86S 8 ett e%I 9 $07 10 0S3 1334 791 m 30$ 00 list ll97 7 12M 8 1252 5 1278 3 1303 8 1378 9 1379 0 1479 7 1400 1 1531 7 Ne l 16374 1641 4 174 4 ' s 0 4434 1 5950 1 6068 I 6396 i H98 I 6973 1 7233 1 7476 1 1928 I 8344 I 8732 4 9099 I 94M i 9777 2 0093 2 0397 Sh lit? 61 92 till? 161 92 til t? 26197 361 92 461 92 $6192 461 92 - 763 92 abi t? 961 97 1061 92 Ill e 0 01785 3 001 3 957 4 76S 4 554 4 sel 5 119 5 392 5 937 4 46$ 6 994 F Sil sN6 S S70 9 093 9 615 1338 08: e 309 75 1189 6 1196 7 1225 0 1251 8 1777 9 1303 3 1328 6 1378 7 I421 0 1479 9 1531 6 1584 0 16377 1691 4 lin 3 ' s 0 4477 I S913 1 6001 16340 l % 44 16922 4 7181 1 7425 1 7877 1 8294 1 8687 1 9049 19J96 19??7 2 0044 2 0347 4 e = . 5a 8 73 $$ 73 tot 73 ISs 73 208 73 . 5 8 73 358 73 458 73 $58 73 654 73 iS8 73 s$a 73 9S4 73 1054 73 170 e 00 189 3 7275 3 7815 4 07 % 4 3610 46341 4 9009 S 1637 $ 6813 6 1978 6 7006 7 2060 7 7096 8 7119 8 1130 9 Pl34 1341 27- n. 312 58 1190 4 l195 6 1274 1 thil 12774 1302 9 1325 2 1378 4 1428 8 1479 8 1531 4 154I9 M637 8 1691 3 1746 2 s 0 4919 i S819 I 5943 8 6286 3 6592 1 6877 1 7137 I 7376 8 7829 1824 I 8635 4 90pl I $349 I 9640 4 99 % 7 0300 Sn 267 5267 10767 15767 20267 25267 3$2 67 4S267 $$267 652 R3 ' 752 67 89 67 9S2 67 1052 67 13B o 0 01796 3 4544 3 4699 3 7489 4 0129 4 2672 4 SISI 4 n49 S 2344 5 7118 6 1814 6 6485 . 7 1140 7 5781 8 0411 8 5033 134733: h 318 95 litt 7 1893 4 1222 S 1749 9 1216 4 1302 1 1327 5 1377 9 1428 4 14794 1531 1 IS83 6 1636 9 4691 5 1746 8 5 0 4998 i$813 I 5831 1 6887 1 6493 1674 I 7037 I 7283 4 7737 i SISS I 8545 1 8911 1 92S9 I 9591 l 9907 7 0211 Sn 46 96 %% I46 96 1% % 246 96 346 % 446 % S46 % 648 96- 7496 846 96 946 96 1046 96 las e 0 01803 31190 3*El 3 7143 3 9526 41644 4 4119 4 8548 5 2995 5 7364 6 170s 6 6036 74349 7 4657 7 8966 (353 04) m 324 % jil3 0 I??o l 1248 7 1275 3 130; 3 1326 8 1377 4 1478 0 1479 1 IW) s IS83 4 1636 7 1690 9 17459 s 0 S071 1579 I 608S 1 6400 1 6686 16949 ' I Fl% 1 765? I 8071 1 8461 I 88 t1 8 9176 1 9508 8 9425 7 012* 4;' *.* .
- 191 9 241 S' '4: S7 44 U 54! S7 641 $7 741 S 7 A41 t
- als N; * *
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- 341 24 6196 0 1215 6 1744 7 1772 2 !?94 8 1324 7 1375 8 lan e 1478 0 INS 1582 6 1636 i 1690 4 1745 4 s OS269 1 $591 1 5823 1 6152 1 6447 16717 16%8 1 7428 1 7850 1 8241 1 8610 18959 8 92$1' I 9608 1 9913 Sn 26 97 16 92 126 92 176 92 226 92 326 92 426 92 $26 92 de 92 726N 82692 916 97 10?6 92 las e 0 01827 2 5312 2 6474 2 8SC8 3 0433 3 2286 34093 3 7621 4 1064 4 4$08 4 7907 S 1783 - 5 4657 S eola 6 1363 4373 08 n 346 19 11 % 9 1713 8 1743 4 1271 7 1297 9 1324 0 1375 3 1426 3 14:1 7 IS29 7 IS82 4 163$ 9 6690 7 1745 3 s 0 $328 1 % 43 4 5743 1 6078 1 6376 1 % 47 I 6900 I 7362 I 7784 1 8176 8 8545 1 8894- 49227 89545 I 9849 Sn 7247 7247 12247 17247 ??? 47 32247 42247 S2247 62247 7??47 8??47 92247 1022 47 -
ISO e 0 01833 24030 24%1 2 6915 2 8756 3 0525 32246 3 % 01 38889 4 7140 4 536$ 4 8577 SIFu S 4949 $ 8174 1377 531 2 350 94 11976 I?!? 0 1242 0 1270 1 12971 1323 3 1374 8 len t 14774 1529 4 1582 1 163S 7 1690 0 174 1 s 0 5384 1 $499 ItM7 1 6006 66307 16581 1 6835 1 1299 11722 I 8115 1844 I 8834 Itru ! 9484 19789 Sa 18?0 6820 Ill ?C I64 20 21820 318 20 41820 $18 20 11820 718 20 818 20 914 20 1018 20 3e e 0 01839 72873 2 3598 J S480 77747 2 8939 3 0583 33783 36915 4 0008 e 3077 46128 4 916S 5 211a S SJM 1381 806 a 355 51 !!99 3 1710 1 1240 6 1769 0 1296 2 1322 6 1374 3 14M S le77 0 IS29 I IS819 1635 4 1689 8 ' 1745 0 s 0 $438 1 $454 1 5593 1 5918 1 6242 1 6518 16773 1 7239 17663 1 8057 I 8476 15776 8 9109 I 9427. I 9732 Sh = Superticat. I h = entfialpy. Stu per Ib v = Speofic volume. tu !! per Ib S = entropy. Stu per F per ;o , z _f, ._.
e= E (f Totple 3. Superheated Steam-Conth:4#ed
$40 $40 kmim4W.b8mif 4WW .
I$al femel flater $leam 4N 890 $N ISO IN 2W ON N0 1000 ligt 12M 13N 1400 ligt h 14 M 64 M 114 99 164 M 214M 354 09 414 M Sle M 614 M Fle M 014 M 9140010leM lil4M 1 + e 4 08084 2 ter! 2 2364 2 4141 25M0 2 Mee 2 9078 32137 3 512e 3 0000 8 1007 4 3915 4 6sil 4 9e95 5 2571 5 5440 Sell ~ b 2091 11990 INS 02 42M 2 IM80 1295 3 1321 9 1373 7 1425 1 1476 7 152s t 1581 6 16352 1689 6 17as s 18eo s
-e s 0 5490 1 5413 A M22 1 5872 1 6100 1 6458 16F15 1 7182 I Mel 1 0001 1 8378 18723 1 9954 1 9372 19677 1 9970
.. h 10 12 4012 Il0l2 160 12 2.0 12 31012 41012 51012 61012 710 12 810 12 910 12 1018 12 1810 12
.'M e 40450 2M 28MO 21999 2 4630 2 6199 2 7710 3 8642 3 Mes 36327 1 9125 4 8905 4 4673 4 74M 5 0173 5 2913 M t Me 17 litt 6 12M 3 1237 8 IN69 129e 5 1321 2 1373 2 tem 7 1476 3 1528 5 Ital 4 16M 0 left 4 lied F ING6 s RHee 15374 1 5453 4 5808 1 6120 1 6400 l 6658 1 1128 8FM3 1 7948 I8118 8 0168 I 9002 l 9320 1 9625 I 9919
$h 6 30 % 30 106 30 IM 30 206 30 386 30 406 30 506 30 606 30 706 30 806 30 906 30 1986 30 ll0h 30 230 e 0 010 % 1 9985 2 0212 21119 2 3503 2 5008 2 6441 2 9276 3 2020 34726 3 7406 4 006s 4 77tl elin 4 Ms4 5 0606 1393 70s h M828 '700 1 420s 4 12M 3 1265 7 1793 6 1370 4 1377 7 1878 2 1476 0 15?8 7 1581 8 16M 4 1649 3 1744 5 te005 s 0 M88 I 5336 I 5385 I 5747 1 6062 I6M4 i Ho4 1 7075 I 7502 1 1897 i 8268 I utB I8%7 8 9270 I 9576 I 9su l
$4 2 61 52 61 802 6l 15261 20261 30261 40261 50741 40268 702 61 80261 90261 100241 1107 64 388 e 0 01860 1 9177 .948 2 0928 22462 2 3915 25316 2 3024 3 0661 33M9 3 5831 38385 4 0976 4 34 % 4 %F7 4 84%'
1397391 h 372 2F 1200 6 202 4 1234 9 1264 6 1292 7 13I1 7 1377 8 1423 8 14756 15279 1580 9 16M 6 4689 1 1744 3 4800 4 5 6 % 34 1 5299 ,5320 I %B7 1 6806 8 6298 I6%2 1 1925 1 7452 8 7848 I 8219 1 1570 l 9904 I 9223 1 9578 1 9822 54 49 03 99 03 149 03 199 03 299 01 39903 499 03 599 03 69903 79903 89903 999 03 1099 03 390 e 0 0lI65 1 8432 2 0016 21504 2 2909 24M2 2 6872 2 9410 31909 34382 3 6837 3 9778 4 1709 4 4131 4654 140s 971 h 37614 1201 1 1233 4 1263 5 1291 8 1319 0 13716 1423 4 6475 3 15276 1540 6 4634 4 1648 9 1744 2 1000 2 s 0 % 79 ISM 4 I % 29 I 5951 1 6239 I 6502 1 6976 I FeOS I 7001 1 8173 I B524 I 8854 1 9177 8 9682 I 9716 Sh 45 % 95 % 145 % 195 % 295 % 395 56 495 % 59556 695 56 795 % 095 54 995 % 1095 % 3e
- 0 01870 1 7742 1 9173 20619 2 1981 2 3209 25a0s 2 82 % 30ul 3 3084 3 5408 3 7758 4 0097 42427 4 4750 1404 441 h 379 90 1201 5 1231 9 1262 4 1790 9 131B 2 137I i 1423 0 1474 9 1527 3 1540 4 1634 2 1608 7 1744 0 1000 I s 05F22 1 5230 I H73 13899 1 6189 1 6453 1 6930 17M9 1 7754 1 8128 lasso 1 8814 1 9133 194M 19732 Sh 4220 92 20 142 20 19220 292 20 M220 49220 592 20 H220 79210 M220 992 20 1062 20 230 e 8 01875 1 7101 ISMI 1 9799 2 1121 223es 24a24 2 7106 2 9509 3 1006 34M4 363st lege3 4 0049 4 3087 1487at b 3R3 % 1201 9 1230 4 1261 2 1298 0 1317 5 1370 5 1422 6 14 F4 6 15278 1500 1 1634 0 leu 5 IF43 9 1000 0 s 0 5764 1 5197 1 5518 1 5884 1 6140 1 6406 1 6085 1 7315 1 7713 1 8085 1 8437 18778 1 9090 1 9396 1 9690 Sh 34 93 30 93 13893 18893 200 93 388 93 488 93 58893 64893 788 93 5093 988 93 1008 93 2e
- 0 01880 1 6505 1 7665 1903F 2 0322 2 1551 2 3909 2 4194 2s437 3 06 % 32sn 3 50s2 37217 3 9384 4 1543 1411 073 h 38712 1202 3 1228 8 1760 0 1289 i !116 8 1370 0 1422 1 1474 2 ISM S 1579 9 1633 8 1688 4 1743 7 17998 s 0 580i I 5166 iSua I 5798 8 6093 1 6361 8 6841 1 1273 1 7671 I 8043 I 8395 I 8730 l 9050 1 9356 I 9649
%. -m m .-=
Sn 35 75 85 75 IH h I85 75 285 75 385 75 485 F5 585 FS 685 FS 785 75 805 75 SBS 75 1085 M 290
- 0 01885 I H48 1 6968 1 8327 1 9578 2 0772 2 3058 25M9 2 7440 29505 31711 3 3424 3 59M 3 8019 4 0106 141425> h 390 60 1202 6 122F 3 1258 9 1288 1 1316 0 1369 5 1421 7 1413 9 1526 5 1579 6 1633 5 1688 2 1743 6 I799 7 s 0 5844 1 Sin 1 5412 15750 1 6048 I 6317 1 6799 1 7232 1 7630 I 8003 1 83 % 1 8690 1 9010 1 9314 8 9610 5h 3265 82 65 13265 18245 282 65 34265 482 65 582 65 602 65 782 65 88265 982 65 1082 65 III e 0 01489 1 5427 1 63 % 1 7645 1 8883 2 0044 22M3 2 4407 2 6509 2 8585 30643 3268 34721 3 6746 3 8764 1417 351 h 39399 1202 9 1225 7 1257 7 12972 1315 2 IM89 1421 3 14736 15M 2 1579 4 1633 3 1685 0 1743 4 1799 6 ,
s 0 5882 15105 I 5351 1 5703 1 6003 I 6214 5 6758 I 7192 1 7591 8 7964 I 8317 83652 I 8972 I 9278 1 9572 Sh 29 64 79 64 129 64 519 64 !?9 64 379 64 4M 64 5M 64 679 64 779 64 879 64 97964 10M to 318 e 0 01894 I 4939 1 5763 1 7044 I 8233 19M3 2 1520 2 3600 2 % 38 2 7650 2 9644 3 1625 33H4 3 H55 3 7509 (420 365 h 39730 1203 2 1224 1 12 % 5 12M 3 1314 5 1368 4 1470 9 14732 153 9 15?9 2 1633 1 1607 8 IF43 3 17994 s 0 5920 1 5076 1 5311 1 % 57 15%0 1 6733 1 6719 1 7153 175t3 1 7927 1 8?80 1 8615 1 9935 1 9241 1 95 % Sa 2669 76 49 12669 176 69 276 69 37669 476% 516 69 676 69 77669 876 69 976 69 1076 69 128 e 0 01899 1 4443 1 5207 1 6462 1 7623 187M 2 0823 22843 2 4821 2 6774 2 8708 3 0678 3 2538 3 4438 3 6132 1423 31s k 400 $3 1203 4 1222 5 12 % 2 1285 3 1313 7 1367 8 1820 5 1472 5 1536 1578 9 1632 9 1687 6 1743 1 1794 I s 0 5956 1 5048 1 5261 1 % 12 1 5918 1 6192 I H80 1 7116 1 7516 1 7890 1 8243 18579 1 8899 1 9206 1 9500 sh 23 82 73 82 173 82 173 82 273 82 373 8/ 4 F] $2 573 82 47387 F73 82 47382 97382 1073 82 13e = 0 01903 140s4 1468a 1 5915 1 7050 1 8125 2 0168 2 2132 24054 2 5950 2 7828 2%97 3 1545 33389 35227 1426181 h 403 70 1203 4 1220 9 1254 0 1284 4 1313 0 1367 3 1420 0 1472 5 15n 3 1578 7 1837 7 1687 5 1742 9 !?992 s 0 5991 1 5021 1 5213 1 5568 1 5876 5 6153 16643 1 7079 1 7480 1 78 % 1 8208 3 8544 18E4 1 9171 19su Sh 21 01 F101 121 01 71 01 27101 371 01 471 01 571 01 671 01 771 01 87101 97101 10?!01 388 e 0 01908 1 3640 1 4191 1 5399 1 6511 .7%I 19%2 21463 2 3333 2 5175 2 7000 2 8811 3 0611 3 2402 3 4186 1428 991 h 406 80 1203 8 1219 2 1252 8 1283 4 112 2 13M 7 1419 6 14?? 2 1525 0 1518 4 1632 5 16873 1742 8 Iits 0 s 0 6026 14994 1 5165 1.5525 1 5836 l6114 1 6406 1 7044 1 7445 1 7820 1 8174 1 8510 1 8831 1 9138 1 9432 54 1827 6827 118 27 68 27 M827 360 27 46827 % 8 27 66827 768 2F 06427 968 27 1068 27 als e 0 01912 1 32 % 13725 18913 16002 ,7028 1 8970 2 0832 22652 2 4445 2 62L9 2 Moo 29730 3 1471 3 3205 (431 73) h 409 83 8204 0 12i? 5 1251 5 12824 311 4 1366 2 1419 2 14F14 1524 7 1578 2 1632 3 16878 1742 6 1798 9 s 0 6059 1 8968 1 5119 13443 15797 16077 1 6571 1 7009 1 7411 1 7787 1 8141 1 8477 18798 1 9105 1 9400
$h 15 59 65 59 115 59 165 59 265 59 36559 46559 MS 59 46559 765 59 865 59 965 59 1065 59 118 e 0 01917 12891 1 3285 1 4454 I H21 16525 1 8421 20237 2J009 2 37M 2 5482 2 7196 2 8898 3 0592 3 2279 1434 416 h 412 81 1200 1 1215 8 1250 3 !?81 5 1310 6 1365 6 1418 7 1471 5 1524 4 15779 1632 1 1686 9 1742 5 1798 8 s 0 6092 34943 1 5073 1 5441 I 5758 16080 I 6536 I6976 1 7379 1 7754 I 8109 I 8445 I 8766 I 9073 I 9368 Sh 1039 60 39 11&M llo39 260 39 36039 460 39 MO 39 46039 760 39 860 39 96039 1060 M 1st e 0 01925 1 2218 12472 1 3606 1 4635 1 5598 1.7410 1 9139 2 0825 2 2484 2 4124 25750 2 7366 2 8973 30572 44396D h 41859 120s4 1212 4 124F F 1279 5 1309 0 1364 5 14t F 9 1470 8 1521 8 15774 1631 6 1686 5 1742 2 1798 5 s 0 61 % 1 4894 1 4982 1 5360 I % 83 I 5969 1 6470 1 6911 1.1315 I 1692 I 8047 I 8384 I 8705 I 9012 1 9307 .
Sh = Superhett. F h = enthatpy. Bla per Ib v = Specific v0lume. cu ft per Ib 5 = entropy. Blu per f per Ib 3 9 t s t Q-- - - ii
. . , -. 4 e*
3 M - T) Y Table 3. $4sperheated Sleem-Centinesed - d 3 A0s Pre 95 Lll/5418n $4t $al ' W rat m MrMsfa W d W N0 1000 IIN 17N IIM 14N 9500
]
15at temp) Walet 51eam 850 ' 500 550 GM SSG 7W a
+ .
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r tov 1 4 L E n eloSuce U. .S. NUCLEAR PEGULATORY COMMISSION REACTOR OPERATOP LICENSE EXAMINATION CACILITY: HATCH 11.2-REACTOR TYPE: BWR-GE4 DATE ADMINISTERED: 85/03/11 EXAMINEP: K E BROCKMAN
- APPLICANT: _________________________
-INSTRUCTIONS TO APPLICANT:
the answers. Write answers on one side _only. Uee_ separate paper for Staple question Sheet on top of-the answer sheets. Points for each ques tion .sre indicated in parentheses after the question. The passing grade requires.st least 70% in each category and a final.?grade of_ a t ,: hours afterr least 30%. Examination papers.will be'9teked up :. 4
'the ' exa m i r'es t ion s ta r ts . b +' N .A 5 0F L C'AT E GO R Y % OF APPLICANT'S CATEGORY 9ALUE TOTAL SCOPE VALUE CATEGORY
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- t. PRINCIPLES OF' NUCLEAR POWER 19.cc PLANT OPEPATION. THEPM0 DYNAMICS?
AEAr TRANSFER.At!D FLUID FLOW 20.00 23+00 ________
- . rLANT-DESIGN tJ 8 t,,u u D IN G ean. F Ei Y AND EMEPGENCY SYSTEn3 ..
t9.co ne
-n n- nn 3. INSTPUMENTS AND-CONTROLS 4e
~o 4 PROCEDUPES - NOPMAL, ABNORMAL,
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._~___'on_ _"__.
EMERGENCY AND RADIOLOGICAL CONTROL
'^
.~- ~100.00 TOTALS 7s.co-FINAL GRADE _________________%
All wora done on this eNaminstten .s my own. I have neither
'given not rece;ved aid.
APPLICANT'S SIGNATURE l l
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o 1: PAGE 2 1" ,- PRINCIPLESc0F NUCLEAR POWER PLANT OPERATION,
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~~~~T5ER 667Ud55C5I~HEIT TRd55IER~ 56~5EU56~FL6U QUESTION .1.01 (1.00)
Whichfor the followin3 is NOT CORRECT ss applies to the impact of delayed neutrons on reactor-operations?
- a. When-calculating reactor period, the delayed neutron term'may be-considered: INSIGNIFICANT Ji f the reactivity addition is GREATEP than Beta.
- b. The magnitude of the effective delayed neutron fraction (Beta-bar) is GREATER at EOL than at BOL.
'c. The delsyed neutron frsction.(Beta) is the RATIO of the number of delayed' neutrons produced to the number of fission neutrons produced.
- d. The presence of delayed neutrons causes the aversge neutron generation time (1-bar) to INCREASE. . je quESTI0rt 1.02 (1.005 Afsteam condenser must remove more heat energy to con-
.danse ..,(CHOOSE ONE:
- a. ...one pound of steam at 300 psis
- c. , .two pounds of stesm st 400 psis -
- m. ...two pounds of steam at 1200 psia
- d. ...cne pound of steam at 15 psis QUESTION 1 03 (1 00'.
FTP to ~ 0 *' PTP by . Siven A normal power reduction from 00 use of recirculation flow. Which of the following :-tstements is T R f;E' 3 The pressure difference between the reactor and the turbine steam chest INCREASES due to EHC snuttir 3 down.
~
- b. Condensate depr es-:icn OECRE ASES due to the decreased steam flow /losd on the condenser.
- c. Fi r. 21 f eedu s t e r. temp.:r?t uo DECREASES due to the reduceo feedwiter.-heating.
- d. . Turbine efficiency DE C P E A'-iE S due r. o DiCREASED winda Je losses in the low pressure ~ 5 t r 3.z + .
l b
9 f;
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PAGE 3 l 1. ' PRINCIPLES OFtNUCLEAR-POWER PLANT OPERATION,
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~~~~Y5EE5667Ud5 C5I~EEdT~TRdU5E5R d 6~EL656"ELUU GUESTION l'.04 (1 00)
Which of the following statements best describes.the operating
= characteristics of an LPRM detector?
- s. . Depletion of.the detector's. Uranium coating causes both the neutron and the gamma sensitivity to DECREASE with. detector age; the resulting neutron to gamma itsnal ratio remains relatively CONSTANT.
- b. Since the detector functions as en ioni:stion chamber and the Largon gas pressure remains-relatively CONSTANT, BOTH the neutron and the gamms ',ensitivity. as well as the: neutron to gamma signal ratio. remain relatively CONSTANT'as the detector ages.
I
- c. Depletion of-the detector's Uranium coating causes neutron sensitivitv to DECREASE. but.has an INSIGNIFICANT effect on tj -
gamma sensitivityI this resolts in ? neutron.to gamma signa 1 cratio DECREASE as the' detector ages. 4 d.. Depletton of the detector's Uranium coating .1as an instgnif-icInt effect on neutron.sensitivitv. but causes gamme sensitivity to OECREAGE: this results in -s neutron te gamma signal rStio INCPEASE es the detector ages. OVESTION ~1 05 <2.00) As cart of the scram procedure- the op er a tor is directed to insert-the SRM'- snd-IPM's. .
- a. Following-I severe LOCA. EXPLAIN how these systems could be (1.0) used to detect gross core damage. ,
bi- EXPLAIN how these systems could be used to provide s crude-indication of w,e r level if level could not be confirmed bv (1.0) nor m al1in s t r um+n t a t i or.. -
([ 7 F j,: y b PACE- 4
- k. '
L14 -PRINCIPLES OF NUCLEAR POWER PLANT OPERATION,
--- isiss56 sAsiCs- REAY isisiFEE Is5 FCGi6 FC6E-QUESTION 1.06' (2.500 The at' ached figure represents a transient that could occur it a BWR.
GIVEN: (1) An'SRV is-manually liftec at time T = 2 min
..(2) The SRV is closed at time T =-4.5-min (3)' 'No other operator actions occur E(4) Recorder speed = 1 division =.1 minute EXPLAIN.the cause(s) of the'following recorder indications:
- s. Pressore OECREASE. (Point A) 6.- Total' Steam Flow REDUCTION (Point B)
(Point C) ;
- c. Turbine 9 team Flow PEDUCTION
~d. Level INCREASE (Point D)' .
*44 e- NER. STABLE Level (Point E)
L. QUESTION 1 07. (1.00) which of -the following is NOT 3 charseteristic of 3nbertticil multiplicstion? 3,. The subcriticst neutron level is directly proportions 1'to.the rie n t r o ri source strength- .
-b. Ocubling the. Indicated count rate b. aecettvitv sdditions will reduce the margin to criticality by sppt o.:1m st elv .one-half . ,
- c. c sc-equal resetivity additions. tt' taker. Longer ror the new
-equil*ibrium count rate to be re3ched, 33 K-eff cporoaches unitv.
- d. If ten ~10) notchei of rod withdrawal tneresse: the SRM count rate by 10 cps- then twenty (20) notches of rod withdrawal will.
tocresse the S R t1 count rate by 20 cps. A95Ur1E CONSTANT ROD WORTH. L n
e
,9 PRINCIPLES OFTNUCLEAR POWER PLANT OPERATION, PAGE 5
- 1.
--- isEEs557s3 sics- sisi iEAsiFEE Es5 FEUi5 FE5s -0UESTION 1 08 (2 00)
The-sttached_ figure shows a basic closed-loop fluid system with its hesd vs. flow plot (BOLD LINES). -The two pumps are identical,
~
vart?ble-speed, radial. centrifugal' pumps. Pump 1 is inittally operating at one-half' speed to suppiv flow to component 1, as shown.
- a. . Component 2 is placed into. service. thereby increasing the system
' he atD-load. Woeld total power consumption be less by ...(CHOOSE.ONE)
It) Doubling the speed of Pump 1 (2) Starting Pump 2 et one-half speed (0.5)
- b. Which Pump Curve -A, B. C, or 0 - most accurately shows BOTH (0.51 PUMPS operating to supplv the system flow? #
c '. With only Pump 1 oper ating st one-half soeed - If component 2 were throttled open from its initial position. would the system (f_ flow INCREASE, DECREASE. or.PEMAIN THE SAME? (COMPONENTS 1 &2 (0.5)
-ARE IDENTICAlli ,
- d. Given one operating pump, that is chin 3ed to e POSITIVE DISPLACEMENT-pump. Is ihe correct Pump Curve to reflect this Curve A. B. C, or 0? (0.51 GUE9# iou 1.0o (l.YO)
. MATCH the appropriete Thermal Limit (a-ci.
2 . Linese Hest Generation R3te (LHGR) b '. Average Planar Linear Hest Generation Rete (APLHGR) j
. Minitium Critical Power Ratto (MCPR) to e3 h FAILURE MECHANISM. AND to each LIMITING CONDITION given below*
' FAILURE MECHANISM LIMITING CONDITION F1 .Cisd melting caused by Lt. Coolant transition decay' heat d. stored heat botling following a LOCA L2. Clad plastic stesin FC, Clad cesekin3.from the surface 1%
becoming vaoor " blanketed"
. Clad ca sck ing caused bv L3. Maxtmum clad temp-F '3 high stress from pellet ersture of 2200 des F eepansion
13 1 x,; PAGE 1 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION,
--- iqEER557sisiEs, sEAi isi Fss is Es5 FEUi5 FE5E GUESTION 1 10 (1.00)
Which of the.following describes the changes to the steam that occurs between the inlet and the outlet of a REAL turbine?-
- a. Enthalpy DECREASES, Entropy OECPEASES, Quality DECREASES
- b. Enthalpy-INCREASES, Entropy INCREASES, Quality. INCREASES
- c. Entnalpy CONSTANT , En,, copy OECREASES, Guality DECREASES
- d. Enthalpy. DECREASES. Entropy INCREASES,.00ality DECREASES ir 4
9
c s . k DRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 7 1.- ~
~~~~iEEE566iOI55C5~~EE5T iR5U5EER"5 6~ELU56"ELUU QUESTION 1 11 (1.00)
Given the following Power History: roo . 13.ews L ,. 56' k*I*) C '
. 3o 6 'a so ic ';
. ,. 6 3 r mt ( w.e s) . .:. 6. is, .,, .,,
Select the most accurate curve displaying the e::pected XENON transient. i 4 - A, 3.9 .. W Ls o .. 66 se o se se se se C '.. ' e ' = . 3 $. s. T ivt t t h... sl tg..,
- i. .. .
(ee.t 5 5 5 5 . . 5 3 3 5 E F 0 se ss w go g s e, s to gs ge . . . i., og, ig, q, *s g T gm E ( % ..g) Eg., lo w a C. bc-O 4 LS M gg %@ 44, 16 kb N '% b *l g %(g 6gg Sq .g Ti m e (w. . . si Eg... bn - Ca ** -
- d. . , , . . . . . , ,
O 44 %. Ib ,g %b b& TS W BO OO '% b4 h& S$ kg TOM E (h w.%I
r: y gv l w ~ 39p m, _ PRINCIPLESuGF' NUCLEAR ~ POWER PLANT OPERATION, PAGE 8 l '. -
~~~~fsEE56675dsfC57~EEdT TEd 5FER d 5 ?LUi5 Et54 QUESTION 1.12: (1 00)
Which,of-the_following accuratelv describes s' benefit of the Control Cell Core (CCCi? c.- 'The Capacity Fsetor is increased due to'the elimination of
. cod pattern exchanges.
b.- ' Operations are simplified since fivx shaping is no longer required.
- c. Thermal Lim'it margins are. increased due to the elimination of 411 high power fuel bundlet.
-d.-LFoel reliabilitv has been improved due to the increased PCIOMR
-ramping rates which have been incorporsted. -
t AUESTION 1 13 (1.00) is e A ceactor hest balsoce was performed (by hand) during the 00-08 shi ft doe to,the Process Computer being 000 The GAF's were computed, bot the APRM GAIN AO.fuSTMENT9 HAVE Not SEEN MADE. , Which of the.fc.llowing-statements is~TRUE concerning reactor-power 7
- a. If the feedwater temperature used in the Mest balance calcu-13 tion.was LOWER thsn the actual feedwater temperstore. then the ac tual power is HIGHER thsn the correntLy calculited power.
- b. .If.the reactor recircolstion pemo haat inpot' usod 2n.the heat
- a i mee e s levia t tan -is OMITTED,- then -the actoal' ,ower is-
.L30EP then .the cor rently c alculat ed power j-
- m. If-the ites.9 f'ow used in the heat 'a s t ince e s icu l a t ion wa s
-LOWER thsn the actosi steam flow, then 'h+ ectual_oower is LOWER
'than the correntLy csteolated power.
d.' If.the PWCU return temperature used in the heat bal'ance es1-colstion was WIGHER thah the sctost RuCU return temperature. then the ectual power is LOWER than the-currentlw esiculated power,
- r. _
- F PAGE o 1, PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, '
~ ~
~~~iUER b67h EC5 IHEdT iRd 5EER dO6 fEUfd'EEUh t .co GUESTION 1.14 .( W )
Given*. Reactor Power. 60% Core-Flow 40%
-T (Tav) .:
Fuel. Type. PSn8R-Ma> Flow Rate 107% Figures 5 4, 5.5, 5.4 Enclosed (1 0) 0 ;_ M C " .. . . . : C;;C C ;; C N - ' (1) 1.?31 g g&1
.(2) 1 ..
L.537 t
- d. If the MCPR Peintont from the Peccess .omputer ror Rod 20-17 r9sd,'
15 0739' which of.the followin3 would be required per Unit 2 Tech Specs? (1) NC-Actton Peovired ,
'0) Inittste corrective sction within 15 mini.tes and continue the corrective sction so that MCPP 13 wilhin the applicable limit 4tthin 2 hcorse or reduce therm?1 power to 25% wtthin the t.e ;t - 4 hoocs.
- 1) Initiate corrective Jction within 15 fiinutei and continue the corrective sction so that MCPP is within the applicable limit wtthin 4 hoocse or redoce thermal power to 25 w t th in the ne: t G ho..r?. .
- 4) P1:ce the cesctor in HOT 1HUTCOWN w i th t n 2 : tour 's ind 10%
reduce eterm come pressure ,to ' 735 psi 3 and core flow to 4tthin the next 4 hours. e GUE? TION 1.15 11 00; The ristion.procets in a c o metie r c i a l reactor recotaet the neotrons that are ' born' bv fission to be " t h e r m s 11::ed . ' The interaction in t :1.t r e s c t o r c o r e w h i c h ti most erficient in ther m a l t ::In 3 neutr ons f o r . f i .s s i e n occun'with the .../CH00?E OtlE-4 OnGEN a t o m '2 -tn the water moleevie;
- b. . DO P 0 tl stoms in the control rods
- . ICRCONIUM atoms in the fuel c liddin 3
- d. .HYOROGEN stoms in the watar molecules
.2.> , m i
.i-PAGE 10
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
'GUESTION- 2.01 '(3.00)-
With the plant operating it 100% power (Unit-1) and recirc in Master Manual.' arr oper ator Inadver tantly DECREASES the ' Pressure Set' bv 5 psig.- LIST the INITIAL. response and the FINAL Status of the ~ following parameters due to.this. action. -Brief1v EXPLAIN the reasons
.. f o r these responses. F i .j u r e - ? . 4 ( ' ' i s a t t a c h e d for reference. ,
NOTE: ASSUNE-NO CORRECTIVE OPERATOR ACTIONS ASSUME'TCV STARTS At THE 100% STEAn FLOW POSITION Use the PttBehed hBndout Page to answer the question.
- 4. -TCV Posit, ion b.. BPU Position i
. c ~. : .Ecwer
- d. Pressure g,4 0'IES TI0tJ 2.02 +1.00t .
Osckup Scrim valves provide a r edund. ant me ans o r senting air from the. scram pilot valves and scram dischsr3e valves. These backup v:419e 4 ' a r e ...' CHOOSE ONE) s, , .ncreer11y enerji ed and will de-ener ji.:e opon i RPS Scram utgnal.
- b. ... aligned such-that two valves in iertes. one # om each RPS
*rr,p <n-annel. must actuate to vent the serim atr header.
- c. . design.*d toch that both RPS channelt must trio in order for ...
.?nv one or the valves to .3ctuate.
-d. ... powered f r o ni the RE'S Buses A and B.
14ESTICN. 2.03 (1'.00) Diesel genersters A. B. and C have started and sre running in l r e t .s o n 1 e to a Hija Drywell Pressure ilgnit on Unit 2 Whtch of the followin3 conoitions will NOT= trip tha dreavl 3enerators?
-2 Loss of E.<c i t a t io n
- b. Nigh Offferential F.rreent
- c. ow Lo'e e Gil Pre 31 ore
- d. Engine Over-speed ;
-=
?7,. ,p-e PAGE 11 0.- ' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS' ______ 4 GllESTION 2.04 (1 00) The peactor' Recirculation Pump seat cartridge essemblies consist of two sets of sealing sur f aces and breakdown bushing assemblies. Failure of the #2 seat ev$etibly at rated conditions would result in ...(CHOOSE ONE)
- n. ....an INCREASE in #2 seat cavity pressure from approximately 300 psig to approximately 1000 pais.
- b. ...e OECREASE'in.02 sest cavity pressure from approximately
'G00 psig to approntmately 0 psig.
- c. ...an INCREASE in 61 sesi esvtty pressure from approximately 900 psig to approntmately 1000 psis.
...a DECREASE in ti teol cavity pressure from approntmately d.
900 pais to approximatrelv 0.pnis. (/ (10ES TI0tl 0 . 0'5 "2 00) LWith regsed to the RBCCu System: 1 STATE the relative relittenthtp between P. h e FBCCW systam pressure and the pressure (s) or its heet sink and loads. EXPLAIN whv this I1.0) r e l'a t t ensh t ? L4 desir1ble.
- b. LI3T two 'Oi loads cooled by PE:CCW on Unit 2 that are NOT cooled t1 0) o .* R O C C'J on Unit t.
_ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _t.
g , PAGE 12
'2. -PLANT'OESIGN' INCLUDING SAFETY AND EMERGENCY SYSTEMS 00ESTION 2.06 (1 00)
The Hi.jh Pressure Coolant Injection (HPCI) System.utilices 3 iteam turbine to drive a pair of centrifu3al pumps to inject water into the reactor pressure vescel onder emerjency conditions.. The osin HPCI pump ...(CHOOSE ONEi
- i. ... takes tts suction directly from the CST and dischsr<3es tom the ,
HPCI booster pump. which then ' boosts' the pressure-hi3h enou3h for reactor injection. ,
- b. ...t.3kes'its suction from the dischar.je of the HPCI booster pump which_
shares a common shaft with the main pump vis a speed reduction coupler.
- c. ...dischsrjes. at least. 'M00 jpm it rated pressure into the '
'A' feedwater line. upstream of the feed header flow detectors. .
- d. . ...is driven ey a two-sttje. Terry'turbiner ahtch receives its 94 Steam suppiv from the 'B' main steam line. downstream of the flow rettrictors. i
-00E5 TION 2 0' (1 00)
Peactor F Hd Pump iRFp) turbine speed Ls controlled by either e Motor Speed Chan.3er (MSCs or sn Electric Automatic Positioner IEA: . The EAP . . . t CHOOSE OtaE )
- s. ... will control the PFF turbine's seced ontv 1 +- its speed ft;nti it jrester than that from the dGC.
D. ..is normally used to control feed flow ryte over r turbine '
<poed of 0 - 5500 rpm.
-. Unitke the MSC. does cl0 T afford the esp acilitv of .n anval speed control bv vae of a local handwheel.
- d. ...will lock tn piece to prevent a eemp res9onse to a false st3nst. if~1t loses its sv3nn! from the flow cont
- aller.
l _________1_____._1_______________
v. y ll} .
~
~5 & .
PAGE 13
- 2,- PLANT.DESIGW< INCLUDING-SAFETY AND EMERGENCY SYSTEMS
~ GUESTION l2.08 (1;00)
Which of.the following lists of responses (a - d) CORRECTLY. describes the m. sin turbine's response to en GUERSPEED~ condition? RESPONSE 9 4PEEDS (1) (b) (c) (d)
'hester' All ICV's All ICV's ' Master' 102%
ICV'-s begin begin.to begin to ICU's begin , to' throttle throttle throttle to throttle
' Stave * '91 ave'
. ICV's-begin ICV's begin
*o-throttle to throttle All ICU's t11 ICV's All' ICV's All' ICV's - ';
Full Closed Full Closed F'>ll Closed Full Closed 110% Mechant:al . Electrical hechanies) Electriesi-0'Spd Trtp 0'1pd Trip 0'1 9 d Trip 0' Sod Trip 111.5% Electricsl Mechanical. Ela:tric?1 Mechanical O'Spd Trip 0*9ed Trip 0' Sod Trip 0'Spd Trte GUE37 ION- 2 0c <t,go> E e 'j l e d t n +j~ the Standby C14 Teestment SVstem /SCTSi! LIST t h +3 two ( C 's automatic actions whlen will occur in the oper -
- 4. 6 tog train Of 3CIS' 'J i '/ e n th9t the delUse iPPinklePs f0I 'bh8D LP?in l'eceive 3 valid initi3 tion sign?l- .
e m _ - - - _ _ _ _ _ - - . - _ . _ . - - _ _ . - _ . _ _ _ _ - . . _ _ . -_ _ . . _ _ _ _ _ . _ _ A
?
PAGE 14-
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
- 0UESTION_ '2.10 '(1.00)
The..Drywell: Pneumatics System is operating in its normal-line-up 4(Mode'B).. Pressure DECREASE 31(to approximately 100 psig). The 5.ystem will' automatically align such that ...(CHOOSE ONE)
- o. ...the-back-up' Nitrogen supp1v line isolation valve (F001A) w'ill GPEN and the bypass valve IF0018) will.CLOSE.
~
b.. L...the back-up. Nitrogen supply line isolation valve (F001A> will~-OPENcand the. bypass valve (F001B) will GPEN.
. c .; ...the.Essentiel/Uninterruptable Instrument Air supply line itc13 tion valves (F02c & F0531 will OPEN.
- d. ...the Non-essential /Interruptable Instrument Air supp1v line isol.stion' valves (F036 a F036) will GPEN and the Drywell Pneumatics .
Compressors will: TRIP snd ISOLATE. i/ OUESTION 2.11 (1.00) Which one.of the following accurately describes t.ow-Low Set 'LLS) logic. .as-applied'at Plant ~ Hatch? q
- s. Lowers BOTH the opening ind closing letpoints of the LLS valves.
- b. Controls the operation of.all relief valves. excepting E and H.
c.- Is activated by a pos t tion switch which confirms .any SRV opening. d.' Is applicable to Unit 2 ONLi. nUEST ON 2 12 (2.004 Regarding the Festdo.31 Hest Pemoval (FHR) Svstem whi'.e opereting in',the Shutdown Cooling (SOC) hode' omp's discharge from STATE.who t* 1s.necessary to prevent the RHF a, (1 0) decreasing below 400 gpm.
- b. -LIST 2 9v.s to which *he sy1 tem will be effected if reactor cressure increases to above 135 psis. (1.0i 1
r PAGE 15 PLANT'DESIGNfINCLUDING SAFETY AND'EMEPGENCY. SYSTEMS 2. Gl.lESTION' 2.13 (1.00) The' Unit-2 Vital.AC Power-120/240 v Distr ibution Cabinet 2A -is normally 5UPPlied;from 600 v Dus 2D through a Battery Charger-snd a Static Inverter.- If the Static Inverter fails ...(CHOOSE.ONE)
- s. ... the-125 vde batterv will maintain power to the Vitsi AC
.Csbinet.for UP to 6 hones.
b.. ...the power supply.can be manually transfered to the alternate 600lv. Bus ~2C /' Vital AC Transformer 2A by depressing a transfer PB.
- r. ...the power supply will automatically transfer to the alternate 600 t Bus 2C / Vital AC Transformer 2A.
- d. . ....the' power supply can be manually transfered to the alternate 600 v Bus'2C / alternate Static Inverter bv depressing a transfer PBf is' OtIESTION 2 14 (1.00)
Unit 1.ts operating at'JR% RTP using Feactor Feedwater Pumps 1A With this' and 1B.- Feedwater Line A 11, isoleted (n0V F006A Shut). condit on. s flowpsth for PWCU ... (CHOOSE ONE)
- s. ...CAN BE MAINTAINED. The RWCU connection to FW Line A is-isolated by removing-the -spool piece between PWCU and the HPCI discharge;- RWCU is opersted vis RCIC and ru Line S. .
- b. .CAN 9E MAINTAINED. The PWCU conn'ecttan *o c4'Lirie A is i sol r +.ed bv :nsnus 11 v ' v alving shut the connect:on between RWCU snd the HPCI discharge.' PWCU ts cper s tod via RCIC and M Line B. ' ,
- . -..CANNOT DE nAINTAINED. The RWCU flow to FW Line A is not tsclable since the RWCU to HPCI discharge connec tion is not valved. -
...CANNOT BE MAINTAINED. RUCU on1v his a disenerge isolation d.
valve on its common discharge header; no FW Line can'be isolated w1thout pecuring RWCU. i y
--^---_.---e.._.____.____ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _
e- ' c,l w.-- PAGE 16: PLANT: DESIGN INCLUDING SAFETY'AND EMERGENCY SYSTEMS
.' 2 . ~
00ESTION: 2.15' (1.00)- t4hich of.the displays of the indicator li3 hts for.ATTS indicate that-the. system is in:its nor' mal operstin3 mode with NO-. ALARM CONDITIONS present? (CHOOSE ONE) NOTE' FIGURES.9.9(3)'AND 9.?(6)'PROVIDED FOR REFERENCE DISPL'AY/ COLOR LITE / PANEL (al (b') (c) (d)~ OtJ/ Green 007 ON/ Amber 007 TRIP STATUS /MTU ON/ Green ON/ Green OUT On/ Red STATUS /hTU-GN/Grwn GUT ON/ Green GUT
. GROSS FAIL /NTV'-
ON/ Green ON/ Clear ON/ Red ON/Grien PGHER/P925 i/ e f
n .;
,. s
( f ( t i , v- . . PAGE- 17 2 .. ' PLANT DESIGNJINCLUDING SAFETY'AND EMERGENCY SYSTEMS 1 g
~ GUESTION 2.16 (14005 STATE:how IINCREASE, DECREASEr REMAIN THE SAME) Drywell Pressure wovid be' expected.to respond to an SRV dischar3e line vacuum breaker STICKING OPEN during ictuation of the SRV. EXPLAIN YOUR
. CHOICE.
i W 43
)
M RAGE 18
- 3. INSTRUMENT 3 AND CONTROLS GUESTION 3 01 (1.00)
- 12 p'. nt :t: ^- _ ;- p r ; :; . _.t. . . . . RCC-Sequence Mode Selector (SMS) Switch in ' Withdraw.* When the last 'A-12' rod is fulls withdrawn. the operator ,ch telects 'A-34' on the Rod Se4vence Selector 'RSS) S to continue the startup. When this is done ... OSE ONE)
- s. . . . the 4 t.n backli Jht s for a11 the 'A-l' sequence cods will extinguish,and the.backlights for -
the 'A-34' sequence rods will illum'in' ate. L
%e.leke.d.
b.- ...the OSCS will specify th , the 'A-14' rods be withdrawn in a specific order, since ' ie withdrawal sequence is hardwired ri Subgroups 3 4 3
- c. ...if 3 ' full-' '~ reed switch for in 'A-12 or A-34' rod ,
e fails.-its r e ge' ed input in the RSCS logic mav be Simulated with the c e' ..e bvpass switen, gjs
- d. .. ;i.' the 'A-34' rods shovid be fullv withdrawn' the RSS iw' .n should then be placed in 'B-12' to allow ,atthdrawal of the OlfESTION 1.02 ( 1 00)
E3ch Mvdrei'11e Control Unit (HCU) het s osi* of normally r.tOSED Scrim astves thSt provide i path.for CRD water during s r&?ctor Scram. The Sersm inlet valves ...(CHOOSE ONEi 4- ,open fastoc thso the Scrim outlet vstves in order to -' provice adeqtate driving force to the CRD mech:-n:.sm to ensure ptIL ttve ierim tnsertion.
'4 ..are oc mally held closed by str cressure and will open bv ssting presavre when either one of the two asso:1sted Scram Ptlot :tr ', a l v e s is deenergi:ed.
O. ...will not orevent thele associated CRD's from Scramming
# t :w f fail *c open, provtdtng that reactor pressure is greater than 200 ps19
- 1. . . connect the 3er am secumulstor to .he >nder-etston port in t.he COntt01 Rod Drive l-
f .. 4 PAGE 19 G. INSTRUMENTSLAND CONTROLS ~ GUESTION' '3.03 (3.00) Assume theffollowing initial rod' position distribution: All c'ods in: Groups 1 - ? see FULLY WITHDRAWN, encept for one: tod in-esch. Group --- 22-51 in Gesup'1 46-55 in Groupc2 and .18-03 in .Gr oup ') (These 3 rods are FULLY INSERTED). All rods'in Groups 4 10 are FULL ( INSERTED Jto posit icre 00 except 'or rod-34-27 (Group 4) which is FULLY WITHDRAWN. Fill in.the following table with the Rod / Rod Group number you would oxpect to see'displaved'in earh PWM window for EACH of the sitvetions
- ( a J- 'c ) . If.'nothing will appear. write ' Blank."
SITUATIONS E4M (a) 'b) (c) j.
' WINDOW 'Inittel Conditions IC with' Pod 34-27 IC with Rod 22-51 (IC) INSERTED to 00 withdrawn toipi' R001GROUC ________ ________ ________
ENSERT EPROR ________ ________. ________ INSEPT ERROP ________ ________ ________
'dITHDRAW~ ERROR. ________
~
GUEETION 3.04 (1 001 The seactcr r nanonl Cantrol System inc!oces several nanval control switches on the 603 Penel; one of these.19 the 'Roo het Notch N eride" (RONOP' . switch. This three posttton switch ...(CHOOSE ONE)
!. . .,.must be held t r. the ' notch overatrie' co:1+1on whila the 'CRD Contedl* switch i Meld to the ' Pod In" o o s t '. t e n tf conttnnors cod o n :- e r t i o n a .1 Ge9 ired.
- o. ... if.h-ld in the ' E'n e r g e n c v Rod la' Soitttone will bvpais til
'ood insart blcd !'etcept thos+ imposed by the R3CS.
~
i.- .,,. tf hatd'tn the 'Emerjeney Rod In' posItton, will illumtnste a r, 3mber light above the s w i t t. h . de s... when used #or erae n 3e..c v rod inserttone bypasses the Ult 344L1e se99AGO'G *imer t. *d n t !e c t i direct 1% On thF Insert but.
'D
- r. ,
- c. .'
-PAGE E 3.- INSTRUMENT [ AND CONTROLS Gl.lESTION -3.05 (0.00)
-Pegardin3lthe SRV's-and the issociated Low Low Set (LLS) logic:
There are three lights.associateciwith each SPV - RED,' GREEN, and.
;AMBEP.- EXFLAIN what each of the different colored - lights indicates, cnd STATE whether each wovId be energized.:or de-ener31:ed during the. timei ts :'iRV wa s open as a reeult-of_ reactor. pressure reaching t.he SRV';-relief setpoint.
GUESTIGH 3.M (2.001 With: regard te the Off-sss Radiation Monitorin.g System;
- a. LIST the three'(31 combin3tions of radiation instrument trip
; signals thatlwill cause an of f-gss System snto-isolation. #
-(1 5)
'3 . LIST--the Off-gaf cystem valve (s) which CLOSE on an auto-isolation.--
., (p.5)
OI.'ESTION 3.O' (1 00)
-Untt,C'ts-tn the process'of a olant startup with ceactor power at 3 *; R T F . SELECT which-one of'the following signal: will result in c Group I Isolation.
4 N sct,or'wat.n level DECREASES to -55 inches beLow instroment-:ero.
- b. MSLLtunnel temperature. INCREASES to 200 des F.
c.. : Rex ter pressure DECREASES-to 825 ps19 .-
- c. Orywell' pressure INCREASES'to 1 85 osig.
o 'lUsSTION
' ? ,0ii It.00i Given1 3 Low C:sT Level on. Unit 1:AND'a High Torus Level on Unit 2.
- Which one of the following accurStely describes'the responses of-the HFCI snd RCIC Systenis?
- 3. BOTH unit;.' HPCI AND RCIC will auto-swap to Tcrus Suction.
- b. Untt 2 4PCI M D RCIC wt11 auto-swap to Torus !vctton* Untt 1 will ?oto-suso fcr HPCI ONLY.
- c. IJn t t i HPr. Atto FCIC will auto-2wsp to Tcros iaction: Unit 2 will auto-swap for HPCI - Or1L Y .
- o. B O TH ori t't s ' 4PCI will'aute-swap to Toros !vctioni FCIC does nct twfp-
- p. - -.
)
g
.[ _
PAGE -21 3 .- INSTRUMENTS AND. CONTROLS.
,00ESTION' 3.00 (1.005 Given: Unit 2.-Ln control of D/G *B' (Surveillance'being performed)
,D/G "B Mode' Switch in TEST Electrteal-distributton-NORMAL (F~ull Power Lineup)
D/G 'Bis.at rated speed and voltage, but not synchronized. when power is' lost.to f160 volt Bus OF. -Which of the following accurately describes the ~ system operation?- s, Bus 2F can be. powered by O/G 'B' when the operator-takes the Output Breaker; Switch to CLOSE and has the' SYNC SCOPE setivated.
- b. Bus CF will be powered by O/G 'B' automatically, after 12 seconds; appropriste. loads will be pick ed up sequentiallv-Eur-OF c an not be powered by O/G 'B' while it is in the TEST' mode, c.
.given-these conditions. {
- d. Bus CF can be powered bv 0/G 'B' when the operstor resets.the ;#,
L'o c k s u t Relav. setivates the SYNC SCOPEt and tak en the Output 1 Break ef
.to CLO9E.
.Q'J E S T IO N 3.10 (1.001
- The ditn-Turbine first stage pressure' switches p'rovide.permissives-and/or' control signs 1s for several plant functions, uhich of the
'd lcutn3 is NOT one of these control.rvnettons?.
- s. a. c_+:treviation Pump RPT breaker trip oermissiv+
- b. RSCG bvpast
- c. RUN LPAF '
4 rsy, 10% C'.oqure Scram bypats i l-
, ~_. c o r a PAGE- 22
- 3. INSTRUMENTSiAND CONTROLS
- QUESTION 3.11- (1.001 The' Recirculation Flow Control System.contains a 44% Speed Limiter to' control Recireviation pump speed under certain plant conditions.
~
This.44% Limiter ...(CHOOSE ONE)-
- c. ...is first activated when to'tal-feedwater flow decreases below
?O%.snd a reactor vessel low water level slarm-is received.
- b. ...is' designed to prevent Recirculation pump cavitation by
-ensuring idequate Net Positive ~Svetion Heed.
- c. ... enables the FWCS to recover reactor vessel water level upon loss of one Reactor Feedwater pump.
- d. ...automaticallv resets.when the _ initiating signal clears to
. enable the operator to restore normal recirculation flow. ,
00ESTION 3.10 (0.001 t,A Wtth regsed to the einit 2 HPCI Svitem:
- a. LIST the two (2) conditions (including setpcints) which will ( t . 0')
tutomattcaLly initiate HPCI.
'b. For each of the situations listed below, STATE whetner HPCI uILL or uILL NOT Automaticstly Inject into the resctor vessel. (1.0)
NOTE: ASSUME NO OPERATOR ACTIONS 3 A33UhE~4NY FAILE0 COMPONENTS uERE IN THE FAILED CONDITION Ar THE TIME OF fHE AUTO INITIATION SIGNAL. 11- The GLAND SEAL EXHAUSTER VACUUh PUMP rai;s to operate.
/2) The r*INIMUd FLOW UALVE fails to soto orsen rativs shot) when svatem condit ions require it to be open.
S) After decrassing to 50 psig, HPCI ?tesm Line Pressure increases to 150~psig.
/4) 'After incrassing to +60 inches- Peactor Vesiot ueter Level decrosses to -60 inches.
M-_____ _ _ _ _ _ _ . . _ _ . . _ _ . _ _ _ - _ . _ _ _______.______.___m___-_-.__________________A____ _ . _ _ _ .
E. . A'
~
-PAGE 23 3.- : INSTRUMENTS ANO CONTROLS OLIESTION '3 13' (1.00)
'The Unit i; Primary.Containmen4 Atmospheric Contr01 System can be used to vent theLprimary containment under normal operating con-ditions'.: To do.this, the operator must manipulate the key-locked ~
. bypass, switches.. The direct effect of doing this. and the method by.which this 11 done. is.to ...(CHOOSE.ONE) 3 7. . .over ride ' the HI' MSL PRESSURE ( >-850 psig) isolation signal iby HOLDING'th.e) bypass switches in the BYPASS position.-
.b. . ... override the HI,MSL PRESSURE ( 850 psig'* and1the LOCA isolation signals-bv1 HOLDING the bypass switches in-the BYPASS position.
- c. .... override the HI MSL PRESSUPE ( 850 psig) isolation signals.by PLACING-the bypasi iwttches-in.the BYPASS oosttion.
- d. . . . override the :HI .MSL PRESSURE ( > 850 psig* andtheLOCA.isolakien
- 4tenals by PLACING the bvpass switches in the BYPASS position.
it OUESTION 3,!A -(1 001-
=uhtch.of the following statements correctiv descrtbes '
, .the protective trip function (t associsted with the Deactor Rec ir'cula tion pumps ' motor generator sets?
3 TheEOC-RPT" trip protects the plant from overpressori stion
.tsinstent5. e.g. MSIV Cloivre2 by tripping the reetrevLation pumps.Ewhen reactor pressure esceeds 1120 psig,
- 9. The $ct'or 3enerator field breaker stays. closed in most instances when the-nG Set drive motor breaker ~ trios- in order to maxim 1:e- .-
coestdown flaw. W. The two 'EOC-RP r
- bre ak er s for each r ec.t r eo t s t ion pomp'sre redondent te. the -MG Set 'dTive motor breaFers. and interrupt power
-tf the M G S e r, dortng overpressori:stion transtents.
d .' Th+- ~r e ac t av recirculation. pumps trip on low low reactor ees sul water *evel,: to-ensore det Positive Svetton Head (NPSH).
. requirements see met.
p; La e y,;' i I PAGE 24-3..: INSTRUMENTS AND CONTROLS i' GUESTION 3 15 < 1 00 )-
.A: reactor startup/ power ascent is in progtess-with the 'B' '
TRM. failed upscale and in.8fPASS. The mode. switch has just been-taken to~*Run". WHICH one of the following-situations / events will cause.1 reactor-HALF-SCRAri?
- o . - AFRM Flow . Converter-(Unit) 'A' goes INOP lb.' APRM 'B' fails 00WNSCALE
- c. One'of the 11 valid LPRM-inputs.to APRM 'B
fails DOWNSCALE'
- d. 'APRM 'B' Mode Switch is taken to STANDBY i s' '
1
/
n~-
'# s
-1 -
PROCEDURES diNORMAL, ABNORMAL', ENERGENCY TAND PAGE 23: lf.-
~~~~Ei6f6E65f65 ESC 6 TR6E~~~~~~~~~~~~~~~~~~~~~~~~
LGUESTION 4.01- -(1.00'. Procedure HNP-2-1?O2, ' Pipe Break Inside Primary Containment *r listsinumerous conditions indlestive of a break. Which of the rollowirg supports r,he suspicion of a GNALL~ break inside containment. _, 5.. Decrease in reactor waterEleveli pressure and/or temperaturenincrease ~ in Drywelli airborne activity increase in Drywelli increased DWFDS
. operating frequency. .
- b. Decrease in aeactor pressorei pressure and/or-temperature increase
-in Drywelli_ generator' load decrease; DWFDS high level.
c.- Peactor.Serim from low water level; pressure and/or temperature
' increase in Drywelli 3ener stor load decreaset increased DWFOS p operstin3 Frequency. #
4 Coactor=Scr?m from high Drywell-pressure; generator 11oad decreased eirrorne activity increase in Drvwe113 DWFDS high level. . DOESTIGN. 4.02 < 1 0 0 *> aictor is at power and the CRD System is Lost. Per HNP-2-1940, The
- ' Loss of.-CRD Systems'. if the operator C AtJ NO T restore CRD flow.
he{<hould ,..(CH00SE ONE)
.a. _.v.. with reactor pressure less than' 800 psi 3,, and more than
' f i n. I5T se;omoletor trouble lights- commence a f ast- re actor . shutdown.
5 ..,, with reictor cressure greater than 800 psi 3- and' rive (5) ,- adjacent accumulator trouble lights or thirty (30' total trouble I t jil t s , manustly Scrse the reactor.
- c. .... wi+t reactor pressure less than 800 psig, and more than t;> c e e (3) iccumulator trouble lights, manuallv $crim the reactor.
- d. ...e with reactor pressure greater than 800 ps19.-and three (3),
. adjacent accumulator trouble li jh's or thirty (30) total trouble lights. commence a fast reactor shutdown, r
i
b;p;,; w4 y; A;p. ~' /
- e R
.f *- *
,. 3 JjN ?4 PROCEDURES - NORMAL, ABNORMAL, . EMERGENCY AND PAGE 24
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~E3656[665CIE."C6NTR6L
\
H GUESTION 4.03 (1 50)
. Procedure HNP-8008 ' Radiation Work Permit'. provides guideance for,where the ORIGINAL copy of RWP's should be' maintairied. ;
MATCH the proper' location with *he tvpe of RWP. TYPE OF RWP LOCATION
- a. Routine RWP 't. (tain Control Room
- 2. Job Site Entrance (Unattended).
i b. Blanket RWP 3. Job Gite Control Point (Attended)
' 4. H.P. Office
- c. Regular P4P 5. R3dwaste Control Room
- 6. Security Building (CAS) 7 4.04 ( .50) !
QUESTION You enter in tres cost.!d with the.following ston' ~
-i i'4#
CAUTION l V g&
.1
.aoievese aos a MEEP OUT ewe ninvi ir se.
tein,
-A + m i r. i m u m . now often should vou resd voor po9 et dosimeter?
o f :E ? ? Id ri . 4.05 /1.00) Re 3 a r d ing H a r,c h procedures, i.n generit. EXPT.AIN uhen vou wovLd espect to see a CAUTION statement AND when you wovid enpect to see a u APU dig s t.i temen t , ' Include the difference cetween the two) k. h. _ . . _ _ _ _ _ _ _ _ _ _ _ . _ . o
(' PROCEDURES L NORMAL, ABNORMAL, EMERGENCY AND PAGE 27 4.
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~Rd65 LU55 eke ~CUNTR L QUESTION 4.06 (1.00)
Procedure HNP-501, ' Equipment Clearance and Tagging', states *
'Under no circumstances is anyone ever authori:ed to attach or remove a red HOLD tag without first having a proper clearance. The only e:tception to this is ... '(CHOOSE ONE)
- a. ...to isolate DC systems of less than 24 vdc.
- b. ...to rack in/ rack out a station service feeder breaker.
- c. ...to isolate multi-divisicnal power transmission circuits.
- d. ...to rack in/rach out bus ties of 480 vac. or less. ,
GilESTION 4.07 (2.00) 5/ Procedure HNP-2-1000, 'Insbtlity to shutdown With Control Pods'. states that* 1
- If it any time. either condition b(1) or b(2) exists, and either _____ (s.11____ or ____ (s.2) ____. and if it is obvious that the reactor cinnot ce shutdown and, in the p.idgment of the Shift Sopervisor. or in his absence, a j licensed operitor, a h a ;:a r d e x i s t s .t o the environs. personnel, or the plant, utill:e the standbv liquid control system ,
l per HNP-2-1400 ...' l 3 LIST conditions ( a.1) and (a.2). (1.0).
- b. LIST conditions b(1) and b(2). (1.0) h
- l. a j.
28
~
'4. PROCEDURES - NORMAL, ABNORMAL, ENERGENCY AND PAGE
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~6d656C66fCIE~C6NTR6L GUESTION 4.08 (1.00)
You enter HNP-2-1910, ' Loss of All Plant Service Water", and a.e unable to. restore PSW operation. Subsequent operator actions require you to place Fuel Pool Cooling in operation at maximum flow. This is done to ...(CHOOSE ONE)
~
- 3. . ~ .
- Provide a long-term hest. sink for RHRSW via the Fuel Pool Cooling Assist connection.
- b. ... prepare for the high heat load from the impending reactor shutdown and required fuel unload.
,c. ... Provide a long term heat sink for TBCCW.
- d. ... p* ovide a short term hest sink for RBCCW. .
I GUESTION 4.09 /1.00) ;,
- 4 A C AUTI0ri in HNP-2-1002, ' Pipe Break Inside Primarv Containment'.
states that:
'A Pipe Break in the Orywell could result in Reactor Level Feading inaccuracies due to increased temperature.
Pefer-to Section 'E' ... for erratic correction method before proceeding. Erratic level indicotton could be due to water in the senstng line fisshing to steem.' Using Section 'E'. enclosed,'and given the following readings: 2T47-R420 102 deg F 2T47-R621 228 des C .' 2821-604A +26 inches 2B21-604B +23 inches
'What'13 the best estimate of Actual uiter Levete
- s. +0-1/2 inches '
- b. +15 inches
. +34 inches
- d. +27-1/2 inches 1
L. . . .
4 '.- PROCEDURES -[ NORMAL, ABNORMAL, EMERGENCY AND PAGE 27
~ ~~~'~~~~~~~~~~~~~~~~~~~~
~~~~Ed656L6656dL 66NTR6L
-GUESTION- 4.10 '(1.00)
~
Both Recireviation Pumps trip. You place the Mode Switch to SHUT 00WN but are. subsequently,-UNSUCCESSFUL in restarting either Recir- Pump. COMPLETE THE'FOLLOWING: (HNP-2-1032)
' Subsequent to Reactor Shutdown. and without both recir--
.culation pumps operating. maintain vessel level from (s) ____. to ensure ,,___(b) ____.
(greator than) ____
~ 00ESTION' 4 11 (1.00)
Procedure HNP-2-1934, ' Torus Water-Temperature Above 05 des F', dtreets:
'If any' point-indicates a torus temperature greater ;
'han or equal to-05 deg F. initiate torus cooling...'
8, Additionallv, . 8,
' Operator should not i n i t. a s t e torus cooling unless
~
water-level.Is ( 14 - and at 3 level _ greater than ___ (2i___.' ,
'Jh ich c f t'he following'ere'the MINIMUM requirements t'or (1) and (2)?
- a. -( 1 ) . Stsble
- 32) that required t'o r Naturst. Circulation
- b. (1) Increasing 2' Top of Active Fuel c., (1)~ Stable-a r2) 2/3 Ccre Hetght /
~
- d. ti) ' Increasing I '. Peactor Vessel 2ero o
L, . . . . . .
. . ....., , . a
o-PROCEDURES - NORMAL, ABNORMAL. EMERGENCY AND PAGE 30 4.
~ ~ ~Ed6f6E66f6dE,~66ATR6E~~~~ ~ ~ ~" ~" ~ " ~~~" "
GUESTION 4.12 (2.00) Place.the following procedural steps from HNP-2-1001 into the proper sequence. as thev would be performed during an actual reactor plant startup and pressort:stion according to the procedure:
- a. Stabill:e reactor power with 1-1/2 BPV's open
- b. Start a Mechanical Vacuum Pump
- c. Open the Steam Seal Feed and Svpess Valves d.' Establish vessel water reject thru the RWCU System
- e. Fisce a SJAE into service
- r .- Start a Steam Packing Exhauster 9 Place RCIC.in Standby, per HNP-2-1123
- h. _ Start Reactor Feedwater Pump 2A (or 20) g ,A '
GUESTION 3.*1 (1.00)
= Procedure HNP-2-4207, 'fransformer Fire'- lists three (3) Operstor Act)gri Steps for a Startup Auxiliarv Transformer fire. Which of
- the followin3 is NOT 4 requiced Gperator Action) 3 Confiam CARDOX system actuated.
- b. M a no -s t l e ' s t .3 r t the required D/G's and synchront:e to the E-bus.
- c. Deenergize.the Transformer.
-d. E eal.u te the clant conditions for possible shutdown.
QUIETION a.14 '.2 004 '. P r o c e d u r e - H rl P 1 0 0 1 , ' Normal Startop". instruct 3 the operator to REAC Later losel select switch
' select level Bi level A to be osed only.when performing main enance or surveillance NOTE
- FIGURE 2.3(2) IS on level B). PROVIDED AS REFERENCE E:(F L AIN - why level 6 is specified,
.GUEETION 4 15 f.1. 0 0 i Procedure 4rJP-2-1437. " Reactor Recirculation Pump Speed Changes". cautions the ooetetor not to? :tsrt an idle cump 50% loop speed.
..n les t the other pump ' ts opersting at EXPLAIN the ressor, for this procedurel CAUTION.
s- _ _ _ _ _ _ - _ _ _ _ _ _ _
a i PROCEDURES - NORMAL, ABNORMAL,-EMERGENCY AND PAGE 31
'4.
~ ---------------~~-------
~~~~E56f6666f6dL C6sTR6t GilESTION 4.14 (1.00)'
Procedur'e HNP-2-1005 " Power Changes', states-that Unit 2's
. licensed maximum thermal power for steady. state operations is 2436 MwT.>
' EXPLAIN'in what instance (s) this maximum power.msy be exceeded and how'this is verified.
Ol3ESTION 4.17 (1.00) Which of the rollowing is NOT regotred to be immediately verified or enecoted by the operat.or in response to e ' Suspected Fuel Element
~
F1 lure'. per HNF-2-103O? s
- 2. 'J e r i f v the Off-gst idiorber bypass valve IF043) CLOSES on an I,4
- Off gas. Pre-treatment high alerm.
.b. 'N e t r y the'Grf-jas stack inlet valve (F057) C'.0SES on an nff-gas Post-treatment high-high-high alarm.
c, '.cet lov t sti tha Orvuell and Poactor Eo11 ding Sump pumps untii 3nalysis can be performed- or the SS's approval.
- d. 00 NOT caject any reactor water to the Main Condenser or
'Redwaste without the SS's approval.
m d-: _ _ _ - _ . A
MASTEV COVN s
?.
PAGE 12 to PRINCIPLES OF NUCLEAR POWER PLANT OPERATION,
~ ~
~~~Is[EU66YU3U5C5"UEIT TR3USE5R 3U6~ELUI6~ELUU ANSWERS -- HATCH 1&2 -85/03/11-K E E:ROCh'M AN ANSWER 1.01 (1.00) b REFERENCE EIH. GPNT, 'Jo l ')II , Chapter 10.1-4A.40 5?.40 ANSWEP 1.02 (1.00' b
PEFERENCE Ste,sm T!bles AN5WER 1 03 (1.001 s c REFEFENCE EIM. GPNT. '> c l '!II . Chapter 1).4-11" Thermodvnamtc1 LP. pp 75-78 ANSuER 1 04 (1 00 c REFEPENCE
- 9. . b . G;NT. '10 1 II. Chspter ?.E; Nuclear ;'cwer Peactor Instrumentatton
?<3tems Handbook. Hatrer & E:eck er Iv. c 44 AN?uEP 1 15 (2.00)
- a. E:y observing the Full.-in and Foli-cut trsvel lights (the operator could detertiine tf geometric distortion nad occured.
Inabil:t, t ce conduct full detector movement would indleate (1.0) P. i . i t i n t e e n,i l is J 3 c o n f L J U f' E t t e n h 3 d o c c u r eo l .
- b. E;v obser.ing the neutron level while moving the nuclear t n s ',c omen t a t io n . A <significant1v HIGHER ( spe r o:: t ma te l v N0 t : m e s count rate would be seen for the UNU0IDED aress of the 1.0) core as oppo' sed r, o the '1C ID E D .
_ r
Q PAGE 33 H1. 'PRINCIPLESiOFENUCLEAR POWER PLANT OPERATION.
~~~~55ER566i d E5I"55 i~iR3U5EEE~ U~EL6 6~iLU5
~ ANSWERS ~-- HATCH 1A2 -85/03/11-R E BROCKMAN
. REFERENCE EIH,L-RG-540 (M.8)
ANSWER. 1.04 (2,50) . a.- . Pressure decrease is from the reduced head losses associated with the steam flow (flow .through the 3RV requires less driving (0.5)
-force).
, b. Indicated total steam flow is reduced since less steam is Th9 SRV 11 upstream of the flow
'seen" by.the flow . r estr ic tor s .-
sensors. - OR -- EHC reduces flow in response to pressure (0.5)
; decrease. RLesi flow is 'seen" by the flow restrictors.
- c. Turbine steam flow is reduced by the EHC system proportionate
'to the 9R'1 r ? lease (int.erictive with pressure control). (0.5)
- d. Level incrosse is experienced in the annulus as the pressure. ' / 0 5 )-
reduction csuses void formations in the core.
- e. (Level reduction is controlled by the FWCS). Level is itsbtlined it a point where the Level error .n a t c a e s the steam flow < feed flow mismatch signal.
(0.5)
#EFEPENCE E'H,~GFNT, VoL UIIr Chapter 10.1 AHsuEP 1.0" (1.00)
- d -
RECERENCE ECH. L-RQ-405 -(15) ANSWER 1 08 (2.00) (0.51
- n. . 42)~- Starting Pump : (0.5)
- b. Curve B (0.5)
- c. INCREASE (0.5)
=d. ' Curve C RFFERENCE Pump Laws
a l PAGE 34 I
- 1. PRINCIPLEsc0F4 NUCLEAR POWER. PLANT OPERATION,
~
II"5E57~ IRE 55f5R EU6~ FLUE 6"FL6U l
~~~~iUEEE667 A ANSWERS -- HATCH 1&2 -85/03/11-K E BROCKMAN ANSWER '1.09 (1.50)
F1. b F2. c F3. a L1. c LO. a (.25 eschi L3. b REFERENCE ~
-EIH, GPNT, Vol VII, Chapter 10.2-23 ANSWEP 1 10- (1 00' d 6 REFERENCE ETH. L-PG-i.57 (3), L-PG-c54 ANSWER 1.11 ( 1. 0 0 '-
b - OP - d PEFERENCE ElH. GPNT e V al VIIe Chs? t er 10.1-83-86 , ANSuEF 1. (1.00) . 1 PEF ER E tJC E EIH, L-PG .175 ANSuEP 1.13 (1.,00) b R EFEREtJC E EIH, L-PQ-667 '10- =- - - -- - . r. -
.~-
PRINCIPLES,0F.(NUCLEAR POWER PLANT OP'ERATION, PAGE 35 1.
~
~~~~i5EE5667UIOEC5I~55dT TRd 5fEk~dU6"_ELUi6"_ELUE ANSWERS -- HATCH 1&2 -85/03/11-K E BROCKMAN t .Oo ANSWER 1 14 .(2.~ )
2 . '!? O d . A . A.
.b. (1)
REFERENCE EIH. L-RO-672 (15); U2 T3 3 2.3 ANSWER 1.15 (1.00) REFERENCE ETH, L-PG-402 !?1 . et D 4 I
r- +- . PAGE .36
- 2. PLANT. DESIGN' INCLUDING SAFETY AND EMERGENCY SYSTEMS ANSWERS -- HATCH'.142 -85/03/11-K E BROCVMAN ANSWER '2.01 (3 00)
INITIAL RESPONSE: Remsin Pt 100% Open -(0 25 r
- a. -rCU's _
BPU's - Open (16 5*:) /0.25) b. Power - Decreases (0.25) c. Decreases (0 25)- si . Pressure - REASON:' Above caused by PCU calling for 115% steam flow. (0.5) ((?50-715); x 3.3) FINAL STATUS At 100% Position (0.25)
- i. TCV.'s -
'(0.25)
- b. BPV's -
Shut (. -Power - Lower ( s l i gh t l */ ) f(9.05) Pressure- - Lower (slightlyi (0 25) d .- PEASON* ~Above caused by the decrease in pressure e nsi power . c :4 u s i n g . BPN ' s te-shut -- PCU cycling to new equil-toetum state -' *45 --015)' - 3.3) (0 5)
.REFERINCE a ;EfH. APNT. Vol VII, Chapter 9.J ANguEP 2 02 (1 00s c
REFERENC~ EIH. .GPNT, 'J o l ' > . Chspter 2.5-7 1 Chap'er.J. -11r14 AN3 WEE- 2.0? (1.00i 3-REFERENCE ECH. L-RG-742 (4) 1-
5l; 4 PAGE 37
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
- ANSWERS -- HATCH-lR2 -85/03/11-K E BROCKMAN ANSWER' 2 04 -(1 00) b .
REFERENCE ' EIH, 'GPNT,;Vol.V. Chapter 4.1 ANSWER -2 05 (2.00)
- a. RBCCW : pressure is lower than both its load and heat sink pressures. (0.51 'This is to ensure that any leakage.from the heat sink or the:potentially contamtnated loads is contained in the RBCCH system. (0.51
- b. Pecircolation MG Set Cooler s
. Reactor Water Sample Cooler '
Pectrevlition Pump dotor Cooler Drywell' Pneumatic System Coolers -(2 @ .O.5.eachi DEFERENCE cEIH r .GPtlT. - Vo l . VIr-Chapter 6.4-2; L-PG 736 (4) ANSWER 2 06 (1.00)
'b-REFEPENCE '
ECH.-L-RG-725 (Fi3 5.3.1); L-RG '30 (7 24): GPNT- '901.UIr Chapter 8,.1 ANSWEP 2,0' (1 00* , d PEFERENCE'
. E CH. ' HNP - -e-14)01 :
1 ANSWER 2.08' (1.001 i REFERENCE EIH .CFNT, Vol. VIr C;u p t e r 5.3-2; Vol. VIIr Chapter 9.4-1?r 20 t - If
PAGE 38 2 PLANT DESIGN.1NCLUDING SAFETY AND EMERGENCY SYSTEMS ANSWERS -- HATCH 1R2 -95/03/11-K E BROCKMAN ANSWER 2.09 (1 00) Hesters Trip-Fan Trips (2 req'd 0 0.5 each ) Isolation Valves (Dampers) Close REFERENCF EIH, GPNT, Vol. V, Chapter 3.3-7, 9, 10; L-RO-748 (4,6) ANSWER 2 10 (1.001 b REFERENCE EIH, L-RO ?52. DCR 80-111; L-PG-734 ANSWER 2.11 (1 00:- +
=
6 PEFERENCE EIH. GPNT, 'lo l ') . Chapter 5.1.II,B ANSuEP 2.12 (2 00'- To pres.ent a l o s s o t' reactor water inventerv to the Torus
~
O.Si I ihrough tiie M i n i nion. Flow 71.** iO.2i b ?OC PCIS '!sives (r000 1 FOO?) - A ij t. o Cloro
-11 r u n n i r,3 RHR Puacs -
Tr 1
% 2d Spr-av '141 v e 'F0:3) -
Avt.c Closes (2 rrq'd 9 0.5 each'. . REFEREDCE E T.H - GPNT. >c1 '! - Chapter 4.a *5 17: GFNT. .
s ; '!I , Chsster S.3.c.3 HNF-2-111a- P6 At45uER 2.11 ( 1. 0 0 '-
t
-PEFERENCE EIH- L-RO-733 , ell. Fig 4 I
i ! l 1 , i 1
+
- r. - .
s
* ' PLANT DESIGNh; INCLUDING SAFETY. AND-EMERGENCY SYSTEMS PAGE 19
. ANSWERS -- HATCH-182 '85/03/11-F E BPOCUMAN
~ ANSWER. 2.14 (1 001 b ,
REFERENCE EIH. CPNT e 'lol VI, Chapter 5. 2 : DCP 83-87 ANSWER 2 15 (1 00) b REFERENCE-
.EIH. L-RG-704-(4)
NSWER 2.16 (1.00) INCREASE'(O'.5) The v s c oi.im breaker provides a direct p a t.h - to.the DRYWELL.~(0.51
-PSFERENCE-l ;EIH. GPNi r uc t '/. Chapter 2 1: MURE0/E9-005/Vol ' , N3 4, Power Pesctor Events,-Jer 94. o 5 (Heten'occurance G/25/82) .
M e t e e I
l;- g ' k, ! (67: r r-L i-PAGE 40 L3i . INSTRUMENTS:,AND CONTROLS ANSWERS _-- NATCH 182
-85/03/11-k E BROCKMAN
! : ANSWER- {3.01 .( 1.00) l: --
. w\ =b.d.
_ REFERENCE EIH. G P N T ~, Vol. VII, Chapter 9 2.3-1,2 ANSWER 3.02 (1 00) d RErERENCE t EIH, GPNT, Vol. V, Chapter 2.5-5,20, Chapt,er 4.2.1-14_.15
' ANSWER 3.03- (3.005 f i) (b) (c) #
04 --' l ROD' GROUP 03 03 N8 SERT ERROR 22-51 22-51 18-03 46-55 46-55 46-55 INSERT ERROR 34-2' Blank Blank /.25 esch) WITHORAW ERROR REFERENCE EIH. 'GPNT, Vol. VII, Chapter o.2.2 ANSWEP L3 2 04 (1.601 d REMRENCE E?H. CPNT. Vol. VIIr Chapter 9.2.1-4,5,11 12 1 i l L ..
c: . i- 'u n f y< r it . PAGE- 41
.3. ' INSTRUMENTSUAND CONTROLS' .
7
-85703/11-M E BROCKMAN
[ . ANSWERS - ' HATCH'182 I: r ANSWER ~3.05 (2.00) f: RED: '- Solenoid-contrel. valve has enersized (0.33); L -De-ener 3t:ad (0.33) GREEEN - Power available to the solenoid control valve-(0.33)- E n e r.3 i z e d . ( 0 . 3 3 )
'AMBEP Pressure in tailpipe O S S p t,i g ) (0.33)
Energi:ed--(0.33) , REFERENCE EIH. GPNT, Vol.. VI r Chapter-5.t.II.B.2 ANSWER 3 06 t2.00* ,
<0 opscale .4i-Hi Hi radiation-teips
[ : 5 4 radiation trip snd i downscale trip
.1. opscale Hi Hi '1 .
l I dawnicale trtps - i from each channel (0.'5 .#each) l b.- 'OffgasSvstemOv_tlethandDrsin valves. OR i .Discner3e salve to ths stack, cocter'condentar and moisture _ , separator--drsin valves, and hoidop line drain vs1.ve. /0 5$
'FEFEFENCE EIH- GPHTV Vol. '1 I , - C 5 a c t e r s>3-21; Vol. '/II . Chapter 7.7-1 ~; HNF-0-2067 ,
g
- ANTugt 3 07 (; 00)
(' ., PERERENCE EIH- GPNT, '!al.- 9 *:hapter. 3.1-FL3 3.U3.; ' L 00 '04, F i:3 9,?(01 ANsuER -3 08 (1.00$
-s REFERErJCE- ~
EIH.~L-RQ-750? OCR 31-t75; GPNT. Vol ' > . Chepter
-1. 5 : JPNT- Vol 9II.
Chapter S.1 i G
c: e
' i; _
*=
PAGE .42 3a . INSTRUMENTS *:.AND. CONTROLS-
- ANSWERS ~.-.~HA.TCH 182-
-85/03/11-K E BPOCKMAN ANSWER !3.09' (1.00)
C.
~ REFERENCE ~
~EIH.'GPNTs Vo1 VI
~
Chapter.7 2? EIH Simuist.or
. ANSWER '3 10 (1 00)
- c:
REFERENCE . GPNT, V o l ')I , C h a p t,e r 5.5-10; o*
.EIH,-GPNT. Vol V, . Chapter 3,1 GPNT._-Vol'VII, Chapters 9'.2.2-11 and 0.2.3-5 i
ANSWER- 3.11 (1 00) 6 c
.REFEREHCE-
' EIH. GPNT.VoL 9, Chaster 3.1-23 ANSuEF~ 3 12 (2 00'.
- i. 1.35 psL3.( .25) in Orfuell <.25) and/or La Lo Level /.25)
-of -55 inches i.25)-
- d .- . /O: 9ILL
', 2 r uILL (1 ) - uILL NOT' :(.25 each('
ca l- uILL-
-REFEFF.NCE .
EEHF GPNT, VOL vip. Chapter 8.1 AM9HEF- .3 13 '1 00: C REFERENCE. EIhr~L-PO-752: DCR 70-d42; HNP-1-1500.
+
F.u
. +.
s. PAGE 4?
- 3. INSTRUMENTSfANDCONTROLS l ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN
. ANSWER .
3.14- (1,00) b - OR - d
~ '
REFERENCE EIH, GPNT,,Vol.'V, Chapter 4.1-26; L-PG ?t4 (14) ANSWEF 5.15- (1.001
.d.
-REFERENCE- -
'E!H, L-RG 719 (6,9); L-RG-700 (10) i h
s G e 4 f I l. y -y $e- p g sp w wy w -yWww-w-w wip- gy v gw-,wg+ ,.w--gwye--2-y vg- 9, v w w$" %or- - + = +M 7-V-'p- d'M Nvi* 4 "
- rem 1&PO---PF %'N'T F
.y s- .
PAGE d4 4a . PROCEDURES - NORMAL,' ABNORMAL, EMERGENCY AND
--- gaaiacaciaat aaaigac -----------------------
LANSWERS -- HATCH 132- -85/03/11-K E BROCKMAN ANSWER' '4.01 (1 00) _d. REFERENCE-ECH. HNP-2-1002
. ANSWER 4;02 (1.00.)
c REFERENCE' EIH, HNP-2-1040, pt i ANSWEP 4.03 <1.50?
-*0.5).
s 1-a (0.5) b.-
/0.5)
- c. 2.
REFEPENCE EIH. HNP-8008 p p '.4 , 7 8
~ANSWEP 4.04 ( .50'-
Every '30 m inu tes - (1/2 credit for mora con se r" s t. i"e c es pons e )
.PECPENCE .-
-GET Handbco . p 25
- ANSuEP .05 (1.00) 10 5)
CAUTION - Equipment damaging conditioni entst WAPN!NG - Personnel Injor. ha:Brds exist (0. 5 ) ~ 5'EFEPENCE EIH,.HNP 0. - 25
,r r^
/
( .' ' pf
- l. -
[; ;A.- ' PROCEDURES - NORMAL,' ABNORMAL, EMERGENCY'AND PAGE '45 F L h ._____________ RADIOLOGICAL CONTROL ANSWERS -- HATCH 1&2- -85/03/11-K E BROCKMAN
- ANSWER ~ 4.06 (1.00) b.
REFERENCE EIH, HNP-501~,1pp 8,15
~ ANSWER '4.07 (2.00)'
(0.5)
- 3) 1. o RP'1 level cannot be maintained
- 2. Suppression Pool water temperature cannot be maintained (0,5) b410w 110'deJ.F
'bi 1.!Five 45).1or more adjacent control rods not inserted below the 04 position- 1(0 5)
- 2. Thirtv-(30). or more total control rods not inserted below '(b.5)!
the 06. position. REFERENCE ECH.'HNP-2-1909 At45WE P - 4.09 (1.00) 4.
.RETEPENCE:
EIH, HNP-:-t?t0 i ANSWEE 4.0 (1.00)
- b. ,
PEFEPENCE-E T. H . HNP-2-1002 LANSWER. 4.10 (1.00)
- 0. 5 ) -
f r om 'leii s e l 'e r o -GR - + ~3' rrom Inst.ument-Zero
-s) r 5'O
(? flow path for) Nytors) Cirev1? tion (0.54 bt e
. *y
-1 NORMAL, ABNORMAL, EMERGENCY AND PAGE' 46 '
6.. ~ PROCEDURES
~~~~E36iUE6656A[~6UUTR6[~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS.- ' HATCH 1&2 -85/03/11-K E BROCKMAN REFERENCE EIH. HNP-2-1932 ANSWER. 4.11 (1.00) c
. REFERENCE
.EIH,.HNP-2-1?34,p1 ANSWEP 4.12- (2.00) d (.25): f. c, :b (.751: 3 ( 25): .h I.25); e I.25); a (.25)
-REFERENCE EIHi HNP-2-1001, pp 18 19, 20 22- 23. 29 29
*6 ANSWEP. 4.13 (1 00) 3 C:EFEREt'CE.
EIH..HNP-2-4207, p2 l l u .
r, . i*
' PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND FAGE 47
-4
~~~~~~~~~~~~~~~~~~~~~~~~ -
~~~~EK6i6[66f65E~C6UYR6L ANSWERS -- HATCH 1.t 2 -85/03/ll-K E BROCKMAN ANSWER 4.14 (2.00)
-*B' is normally selected becsose ? failure in.the 'A/C' side, causing the transmitters to sense a LOW level, would ccuse the following:
A turbine trip on High Level (58') would not occur (0 5)- If 'A' transmitter were selected, a false signal would be (0 5) sent out to the controllers to increase level - Level would centinue to increase-until'the operator terminated the transient With '9' selected, a failure of the 'A' transmitter would not result in level change since the 'B' transmitter has n o t - f .s i t e d . (But still do not have C out of 3 trip available) ' (0.5) Failure'of 'B' transmitter with 'B' selected would cause water level change. but the 2 cut of 3 trip wculd still provide (0.5) protection. REFERENCE EIH. L-PG-706; GPNT, Vol VI, Chapter 5.3 ANSWER 4.15 (1.00) To preclude est3b11shing excessive stresses in-the jet pumps due to flow revetsais - OP - to prevent en:essive tsdial boarin3 losds icn the recire pumps) FEFERENCE. EIH.-HNF- -1477, o5; GPNT, Vol V, Chspter J.1 ANSWEP 4.16 (1.001 Manimum licensed thermal power mav be e::ceeded in the instances of THERMAL SPIMES.(0.5) Veriflestion is acccmplished 6. use of GD-3 Printouts from the Process Computer.(0.5? PEFEPENCE j ! EIH. HNP-0-1005 pp 1,2
r .-
-d s.
PROCEDURES -; NORMAL, ABNORMAL. EMERGENCY AND PAGE -48
- 4.
~~~~R I5 5t55f5KE 55srE5E-----------~~-----------
ANSWERS -- HATCH 112
-85/03/11-K E BROCKMAN
. ANSWER ' 4.N '
-(1 00)
- s ,
REFERENCE' EIH, HNP-2-1930 e
c; 4
- s';
Ub TEST CROSS REFERENCE PAGE 1 7
' QUESTION' -VALUE:' REFERENCE 01.01 1.00 KEB0000065
- 01.02- 1.00. KEB0000066
-01.03 -1.00 KEB0000067 01.04 -1 00- 'KEB0000068 01.05- 2 001 KEB0000069 01.06' ,2.50 KEB0000070 01.07 1.001 KEB0000151 01.03' .2. 00 - KEB0000152 01 09 - -1.50 KEB0000153
'01.10 1.00 KEB0000154 101 11 1.00 KEB0000155 01.12 1.00 KEB0000156 01.13 -1.00 KEB0000157 01.14 2 00- KEB0000158 ,
01 15 1.00 KEB0000159 ______. I 20.00
. 4 02.01 3.00 KEB0000071 02'.02 1.00 KEB0000072 "02.03 1.00 KEB0000073
'02.04 1 00 KEB0000074 02.05 -2.00 KEB0000075
-02.06 1.00 KEB0000076-
~02.07 1 00 KEB0000077 02.08- 1.00-- KEB00000?3 02.00 - 1.00 KEB0000074 02,10 '1.00 KEB0000160 02.11 1.00 -KEB0000161 02.12 2.00 KEB0000162 ,,
02 13 1.00 WEB 0000163 02.14 1.00 KEB0000164 02.15 1.00 KEB0000165
. 02.16 ~ 1.00 KEB0000166 20.00 ~
03 01 1.00 FEB0000080 03.02 1 ~. 0 0 MEB0000031 03 03-- 3 00 KEE0000082 03 03: 1.00 -KEB0000083 03.05 -2.00 KEB0000034 03.06 2.00 KEB0000085
'03 07' 1 00 FEB0000150 03.08 1.00 KEB0000167 03.09 1.00 REB 0000168 03.10 1.00 KEB00001dc 03.11. 1.00 MEB0000170 03'.12- 2.00 KEB0000171 r
03.13 1.00 KEB0000172
r, - 11 x: l l n' ;
^
TEST CROSS REFERENCE 'PAGE. 2
'GUESTION VALUE zREFERENCE.
03.14 1 00- KEB0000173 03 15 1'.' 0 0 'KEB0000174 20.00 04.01 1.00 KEB0000086 04.02-- 1 00- .KEB0000087-104.03- 1.50 KEB0000038
-04.04 .50 KEB0000089 04.05 l'.00 KEB0000090 04~.06 -1.00 KEB0000091 04'.07 2.00- KEB0000175' 04.08 1 00 KEB0000176
~
-04.09 1.00 KEB0000177'
'04.10- 1.00 'KE80000178
.04.11' -1.00 KEB0000179 04.12 2.'00 - KEB0000180 '
04.13 1.00 KEB0000181
- 04 14- 2 001 KEB0000182 04.15 1.00 KEB0000133 04 14 1.00 KEB0000134 KEB0000135 l>4.1- 1.~ 0 0 20.00 80.00 ,
m J L
- > .I jl lj9 m.
w . e* e s I i
' ,t+ .
E S 6 O 0 L . . C 1
/
R N e _ E C P O @ F E V .
. R R U S G I
llgi- t . l lltIi ll l yl l l l l l , F
=
l IIl _ _ _. d .
) : :i !: l; !: ;: l. :
o - ---- - .. NO Pese 3 m$i o e H r- I-' l VM Pump 7 SYSTEM wC Tl j r*-- System Curve j D ' 5 I _ E O j j a
/ n- .
h / I N / \ .. f Pucp 1 Curve \ 3
. f .
/
J
/
Flovi (Arbitrary Units) : SYSTEM HEAD VS. FL0tt PLOT FIGURE FOR 1.08
. . - . - .,,.r__ , _ . . _ .,. .., , . . _ _ . .m,__ , _ _ , , , , _ . , . _ _ _ . , _ . _ , , , , , , , , , _ _ _ , . . . ._ . . _ _ _ . . .-,_.m. _ _____
m
-- 6 6 g e
+. 8 3
S I-
- t. -
.gll s
II g _1 BB I- gig 3 El 88 e r =
- =
'I i - s
.5l E i
E -i g .= _ =. Es .
. l.
- s E. =
IaI88"',ts55 *
, g t ad k
- [
~
i :- rI ::I'
*"0
- - t y- r , x g - .
. :1 s I s -
e i! l ! ! ! i i e s E B a I I w
._ag 1
g
- d. - - - _ . . . /. . gf. _ _ _ . . . _ _ _ _ _ . _
7ff _ _ _ _ _ _ _ _ _ _ _ _ _ I e i i 1 i er i i e i i g 2 ! l 2 2 2 : 0 $ 0 sac R4 mos s'mi mandizinn men ontvm sac > >su nos man,o t GENERAL ELECTRIC COMPANY PROPRIETARY INFORMATION
. _ . . _ _ . _ _ _ - . _ . - - _ , _ _ . - . _ _ _ . . _ F8@UBE FOR 1. M _____.____ _ _ _ _ __ _ - ___._._.
i . . . . e k r. I E - s R8 E
=8 g .- l.i.l.!.
. i
= - a g!
,= # !IIk titt t
** =
I e' !! s==s=is I ((ni l - 1
~~
s
\ -
a n 't b 5 so 6 Y t l - t
'I l - s l
.. . // - g l I 1 i i i g
0 5 5 0 0 ; d uon GENERAL ELECTRIC COMPANY PROPRIETARY IP: FORMATION FIGURE FOR 1.14
.. 133
. gm .'
.) - 5,31 - SJs - I 3r
- 12. -
i 129 -
, "It 275 127 -
1 L 5 E I 3 I I i >
; i im , '
, i i >
, , l
, 2.,,
e ,, ; .. .. .. FIGURE 3.2.31 MCPR LIMIT FOR SX8R FUEL AT RATED FLOW AND RATED POWER
- l . +
1.as > I e I 1m ,"
^
/
1.3a , 1 1 e i 12s 1
, s' ,
is sa , 1 ,
. ,- i i 1J1 ,'
1 - 1 1JD ,' 1 129 ; , 1 129
, , e' '
,'n .a w i .
- l 527 i i i .n ,,
a u , r MCPR LIMIT rfft *ar .1 FUEL AT RATED FLOW NG '.a ; ED POWER MATCH-2 IIO N EI E'b FIGURE FOR 1.14
, y .,
ANSWER SHEET for Question 2.01 m, , INITIAL RESPONSE:
- a. _TCV position
- b. BPV position I c. Power l I
- d. Pressure r-I- Reason:
s t FINAL STATUS:
- a. TCV position
- b. BPV position
- c. Power ,..
- c. Pressure l
1
,~
Reason:
6 - g g g g ST ART UP - RATE
+ m i diet E [ 9 OPEN BlAS A
^
gPEED MGM TRIP TURBINE SPEED ERROR INTERCEPT y ; ygg,yg ( __ E DEMAND
- sP ED V
_ 1 IV REGULATION + ' SELECT
) .
% FLOW CV REO TURBtNE_ g _ llV REO SPEED g '
SPEED LOAD REJECT 6--" macx, toss or sTATon mmo g S - y --I W
$ ,, 7 ERROR (26% m 3 Mel M
START UP "Y
+
==
N ; RWOTE INCMEC SlONAL (CtoSED WitEN IN ADS) RATE MASTER FLOW #FL8" CONTROLLER _gg g[_ I he [j[.g d l- LOAD SELECTOR MANUAL 4 e AU O = TO RECIRC FLOW - *: -- RUN8ACK ON LOAD REJECT (To reno ne - CONTROL OA ul-- RllNO ACK. SYNC SPEED NOT SELECTED
@ [
O No.2sich STEAM 4 FROM SPEE 8,
~
THROTTLE I ' ELECTOR
'8 PRESSURE CHEST A I - TUR9tNE TRIPPED " " ' " ' ' "
- p inot 3 '
i ' PRESS FO g- > Mov' tv ; j,"$', PRESSURE SET 5 FLOW gg l muW +I
+10 yel PRESS. uC_ZNEC F L8"
- g- I 5 BIAS REO. }I STOP VALVES l I ' gYPASS '
STEAM . + eICLOSED THROYTLE- ; g ~, 8 , VALVE PRESSURE l DEMAND
- ~ _7
,, SMALL gyyggg 7
, CLOSE JACK e SIAS
'8 e.
a* m t& uOsme L-auls _O_'
.O-
- ISf f sevre 9.913) af's neste, tr+, east 6
Am 117 atm lit (3 sang) tr'.sact a etaan Ytst art.seC2 a atasp fts? 4>a LLS Ca C sente an eg;.eaevetta se to cm 3;a, 23a, (as ne ga o- P2 O Pe Fegnee 9 till SFil teams Ltqnts ans pass tutteag l l
'i l
4 4 i FIGURE FOR 2.15
- i. ;
E. EE6CQE_ LEVEL _BE691tjf_GQBBEElQti_EQ3_ye3 Ley _IggIm,;tggyg
- 1. O,btai i Or yu'el! Temper ature Reedilig= f ue time 185' Elevatagon.
Terperature Indicator ETA-* RC.CO givv this ce ding for the north side v.d RT47-RC1 gives th -s -esding for the south (( side.
- 2. Refer to Figuae 1 anri obt,in the correc{ ion f u tor for each A
tawiperature reading. 3, 4 the correcti on f ac tor- found using the North Drywel Temperature Reading frew, ti,e lev.1 Ir.Jieetion shown on Leve Indiretor 2B21-RE.04A. .
- 4. 5- %, correction facter f ound using the South Drywel T er , w at _:r e P +-e d in g f-r ur., the level ...wa . tion shown on Leve
' Ir. fi cai; r 2001 FC040. . .l .
C. The d,erage of thPS.k twi LO: lesiew level t rend a ngt will give ! e gs s j e s t ir... t e ,f the Ac t.:=1 T..siu. *.ier _ eve 2. . dom p cm o0 < 4 A c.e -%dA h c.uc t The AW m op c.. h knew w mm be l. w \e,.%4, b .you , b M v{-a Q\ug,s5 b sk. m . i l FIGURE FOR 4.09 i m .-
r-, Geor laPower al ~- - 7 of 7
.. . T a o . I ' d' .
E1W'.1_1
=.
_t ..i.. a .. i,.. n,_.__i
. u . 1 :. .
_..___,_._m.....g ...
..2..!....t_l
.j._ . .;._ _ _ Li._t_.:.._!_- _ r.i_ ;_._.:_ L L _. L _i. J ...
L u._ _.I. .i tL _.i _;._!_ j_
;._r..u_. ' _.u __.!_.tc.i l..l..i ..
I _../:..L L ..L.I_i__i _. _i i _ u _
- :..L. ji . L
..t.
i i, - i i ! i i i_ i ri i
;_q.j_j..,_p..._t_it.:.;_q.l_j_i._j__J....j_J_!_p p _
r....- j I t_J --! I' __ _I . i ; _rp--k=
-i l i . -
__i. i,l.I_. _I _I i.!
. 6I i i_ __i ! I I i i !
'g I ll 1 i ; i iii! I e i ! I I l __ _I !
. IiI ! I e i _!
i l i ! I 1. - .I l l : .
! !.I i 1 e i i i i i i l i I I i
_i i i J, i 1 .' I l ! 4 . H
}l 1 k i i i i/:
. .1 .l - . l _4 I I I l ___ l 6 ., _ l .4 - i~
- ; '- 1 I I iiI I I I i i i , ;
-'i 1g T i . --i, -:g" l'- i l 1 1 'l i T i-~1 4 T_j;Il -
; l l l ; - l- -
l- ..
;_-t- 4 --l . ...q-u . _i
_t_ ..t.. . i, _ f.4., _. w - - u I I l ___ ! l l l /i f-
~
' . 20 I II ' I I I I I Yl' " I' l' ' '
i I /t- A ..: _4.e - J t
.. II I i I I i i
- a. **
i i i i li - I I I/i- l - . . t. . , i A i- . I'-
'. .I l 1i I lI . i.L_'. !
l. i i i l ii li I i l i I N CI E.". T O l',-
, l li I l l l G_j ( / ; ' .-t ., . p .( l j' y .
, . , , , _ ," ,,-r... n e -
! I I I I(l I i i -I -l l1 r"O" T.21 B6CWAtB ;.,
, _; j I
I '_' I I i_ 'j I l I I
' I-
_ 4.. _ .
. I ! 11 i i i f i1 -I , j l ! i l l_ __ l/l i ;I i _ -
1 .I - , .,_ f i I ' 3o, l !I I I i e 1 i ll l 1i ' I , I l i~f- 1- l ~ 1 .I ~
.- _.Il- _f.~. .~l ! i/'li_I'lI i i I I I il i ! l E"~ -
1 l . I I I I I i. i i I '
.. ll 1 l l l_J l i T I I i !
2 l _l - _,/ t I l .I i i i l ! l T~ t..- 7. 1 4 I j ii,- 1 i
. i / ._!._)_I._i._.
!_ !__I__
i .q~1.. __* +g_ g r-D i _r- l
,., -i-; ,7 j-l rr-
_i .i._ i. . _ _r.. r..i i li i i s i i u. 1 t-E i i .._i_ 0 . - . . . i i . i i; ii i s . ,
- 3; __ T co a ===
=
,/. m .. . . . . . .
a c.. A.e . AUIIM IAMV .et AD
, .... ,. ..e MSS cl.AMet M 5 . ,
A
- p VAfteWAY ,
- kg ieme. congrese.4esee.
13 cos umme , l 2 ,,,, . ... . ...
) .
(- , * M86 j escal N 8'
- p e.3. ese3. NH2. 0.eSt see3s N 35 l NO3s .e#26 N#36 He 26
- M A G A C . E O A D . I i A
,! l l . _ . . i
" * * .u. os.
!'n~ 'l i
i { ( A I ] e l
& .... . oc.c l
I e h 45 I e A
,0 3 ,
u I,.a 3 . - A C
. .S .t. .S...
D t.
' e.e E' . - ) C 59
.. ' 1 t . ,,,, . .
co . ..,. . ,
.. .= !. _ ...s....-
g- *"'
.senesessee.sta *a ass. _**((
ascusse ssegest.acet Q , ,,,, , ., _ 6e3
..E4800 .f90ATO peep 31 gg , pf Nes e fr t Ogut n 1 AP O U.EM IAF p ...
I l 4 1 i FIGURE FOR 4.09 5
4 , T y Tettle 3. Supetheeted Sleem I Aes Prest f Lt/$g la $41. 141 hmper@t-Detms F8hrenhed (Sei lemel Walev $leam 200 250 300 MG 400 450 500 000 300 000 908 1000 1800 1200 g Sn te M las M 190 M 248 M 29s 3 %sM 390 M est 26 590 M 600 26 Me M 8es 26 9es M less 26 gygg g, e 8 01414 333 6 392 S 422 4 452 3 482 i Sin 9 M17 $715 631 1 000 7 750 3 set 8 ett 4 979 0 900 6 t 00 73 IIM 8 1150 2 1I 72 9 1195 7 1218 7 1248 8 IMSI 1208 6 13M I 1505 1433 7 1483 8 1134 9 1506 8 1639 7 a El3M 1 9783 2 M09 2 0041 2 1152 2 144S 2 1722 2.1985 2 2237 22700 2 3144 2 3558 2 J9M 24M6 2 4640 2 e969 Sh 3776 8776 IU 76 18776 237 M 20776 337 M 437 M S37 M 63776 73776 837 76 93776 103776 8 , 0 01641 73 53 78 14 64 21 90 24 9625 10224 18023 114 28 IM IS 138 08 190 01 lei te 173 86 105 78 19770 007M n 130 20 till t 1144 6 1171 7 IIM 8 1218 0 1241 3 1264 7 1208 2 1335 9 1384 3 . 1433 6 It13 7 ISM 7 ISM 7 1639 6 s 02M9 14e43 1 8716 I 9064 I 9369 I 9064 I 9043 2 titt 2Sete 20032 2 1300 2I1M 2219 2 262) 2 2006 2 alm gg In 6 79 56 79 106 79 1 % 79 206 79 256 79 306 79 406 79 506 79 006 79 706 79 806 79 906 79 1986 79 1893 lit e 0 01659 38 42 34 W 41 93 44 90 48 02 SI 03 54 04 57 04 63 03 09 00 74 to GO to N 91 92 87 98 M n 161 M 5143 3 1846 6 1170 2 1893 7 1217 1 1240 6 1264 1 17878 133S S 1304 0 14334 1483 S 1534 6 1506 6 1639 % s O M36 3 7B79 1 1928 I 8273 i 8593 1 8092 1 9173 I 9439 I 9692 20!M 2 0603 2 1011 2 1394 21757 2 2101 2 2430 14 696 54 38 00 80 00 138 00 let 00 230 et les 00 308 00 400 00 588 00 688 00 780 00 888 00 948 30 e SI67 76 799 20 42 30 52 32 60 34 67 36 72 30 77 42 86 46 SJ SI 00 SS 06 59 13 63 19 67 h G12 001 a 18017 11Y15 4164 8 1197 6 1216 3 1739 9 1263 6 12074 1335 2 1383 8 18437 14834 1534 5 15s6 5 1419 4 s 3121 1 7S68 1 7833 1 8158 1 8459 1 8743 1 9010 1 9265 1 9739 2 0177 20$s5 2 0969 ! !337 2 1676 2200$ 19 54 3697 M97 436 97 l86 97 2M 97 29697 30697 40697 50697 6M 97 FM 97 N6 9? 9h 97 e 0 01473 25 290 27 837 79 899 31 939 33963 35 977 37 985 41 906 45978 49 964 53 946 57926 61 905 6S an? 01303) a Ill ?! 18S0 9 1168 7 1892 5 1216 2 1239 9 IM36 1787 3 1335 2 1343 8 1433 2 14834 1534 5 1586 S 1639 4 5 0 3837 1 1552 1 7809 I 8134 i M37 I 8770 1 0908 I 9242 3 9717 2015$ 20%3 2 0946 2 1309 2 1653 219s7 3 Sn 27 04 72 04 I?2 04 172 04 222 04 272 04 372 04 472 04 572 04 47204 772 04 872 04 972 04 e 0 01683 20 087 20 788 22 JM 23 900 PS 428 M 946 20 4S7 314u 34 465 37458 40 447 43435 46 420 4940S QU 96) a 1 % 27 1156 3 IL67 8 1191 4 1215 4 1239 2 IM30 1206 9 1334 9 1341 5 1432 9 1483 2 1534 3 ISM 3 1639 1 s 0 3JS4 1 7320 1 7475 1780$ 1 8118 88317 18H6 18921 1 9397 1 9836 2 0244 2 0628 2 0991 2 1336 28kS 5" 9 93 5993 09 93 159 93 209 93 259 93 359 93 459 93 559 93 65993 759 93 85993 9599 a 25 e 0 01693 16 303 040 078 16 SS8 17 429 9 076 20 307 21 527 22740 25153 27557 21 954 32 M8 34 740 37 130 39 S14 . h 20s $2 1160 6 11656 Ilio 2 214 5 IDSS IM25 1206 4 1134 6 1383 3 l4n 7 1483 0 1534 2 1586 2 1639 7 s 0 3535 17141 1 7212 1 7547 Fl% 1 8145 1 8415 I M72 1 9149 1 9588 1 9997 2 0381 2 0744 21009 2 1418
~
H 54 4966 99 % i49 66 99 66 249 M 349 66 449 66 S49 H 649 a4 74g H 849 66 949 H e 0 01701 13 744 14 810 15 859 16 892 7 914 18929 20 945 22 951 24 952 26 9st 28943 30 936 32 9/7 G50 341 a 214 9) 1164 8 1189 0 1213 6 12378 Mit 1285 0 1334 2 1383 0 14M S 1482 8 1534 0 ISM I 1639 0 s 0 X82 1 6995 1 7334 1 7647 1 7937 8210 18467 1 8946 19386 1 979% 2 0179 2 0543 2 0888 ? !?!?
- e . .
36 Sh 40 ?! 90 71 140 Fi 190 ?! 240 71 340 FI 440 71 540 71 640 71 140 ?! S40 71 940 71 gSg 29, e 0 01708 11 096 12 654 13%2 le 453 15 334 16207 17939 19 642 21 379 23 092 24 803 M 517 28??0 h 228 03 1867 1 4181 8 1212 7 !?)7 7 1261 3 1285 5 133J 9 1342 8 1432 3 1482 7 1533 9 1506 0 1638 9
. s 0 3809 1 6872 1 7852 1 7468 1 7761 1 8035 1 8294 1 8774 1 9214 1 9624 2 0009 2 0312 2 0117 2 1044 Sn 32 FS 82 75 tN FS 182 75 232 15 33275 43225 532 75 632 75 732 75 432 75 932 75 40 , 0 01715 10 497 18 036 11838 12 624 13398 14 165 15 685 17195 18 699 20 199 21 697 23194 24 689 G67258 n 236 la 1169 8 IIB 6 6 1211 7 12M 4 1260 8 1285 0 13336 1382 5 1832 I I442 S 1533 7 1585 8 1638 8 s 0 3921 1 6765 1 6992 1 7312 1 7604 1 7843 1 8143 I M24 19065 1 9476 1 9060 2 0224 20569 2 0099 49 54 25 $6 75 % 12$ % 75 % 225 % 325 % 42S 56 525 % 625 56 725 $6 825 % 92S %
G74 44i e 0 01728 9 399 9in to 497 11 201 .1 892 12 577 83 932 IS 276 is 614 17 950 19 282 20 613 21 943 h 243 49 lg77 3 3185 4 1230 4 1235 7 .250 2 1284 6 5333 3 I382 3 1431 9 1482 3 1633 6 1585 7 1638 7 s 0 4021 i H71 1 6449 1 1173 I F471 l 7744 8 8080 1 8492 I.8934 I 9345 I900 2.0D93 2.0439 2 0168 38 Sn 18 98 68 98 188 98 16898 218 98 3t8 98 418 98 510 90 618 98 718 98 41898 91898 GB1021 e 00!??? 8 Sie 8 769 9 424 10 062 10688 il 306 12$29 13748 14 947 16 ISO 17 3SO 88 549 19 746 m non 11741 1184 1 1209 9 12349 12596 1284 1 1332 9 1382 0 14317 1482 2 15334 1585 6 16386 s 0 4112 1 6586 16720 1 7048 1 7349 1 7628 1 7890 1 8374 1 8816 1 9227 1 9613 1 9977 2 0312 7 06S2 55 . St 17 93 62 93 182 93 162 93 21293 312 93 412 93 $12 93 612 93 712 93 012 93 95/ 91 (287 sit e 0 01733 7 945 8 $46 9in 9 702 10 267 il 383 12 48S 13 583 le 477 15 769 16 859 17 94s n 2 % 43 1182 9 12089 1234 2 1259 1 1283 6 1332 6 1381 8 143t b 1482 0 1533 3- 158S 5 1638 5 s 0 41 % I 6631 1 6933 4 7237 1 7518 1 7781 182M 1 8713 I till I 9507 I 987 2 022 2 USS 50 ta 7 29 5729 10729 157 29 20729 307 29 40729 50729 60729 707 29 80729 90725 r292 71) e 0 01738 7 114 2257 7 als 8 354 8 881 9 400 1042% ll 438 12446 13 450 14452 IS 452 16 450 a M2 21 11776 11:16 1208 0 1233 5 12585 1283 2 1332 3 1341 5 1431 3 lati t 1533 2 1585 3 1638 4 s 0 4273 I 6440 . 1 6492 1 4934 1 7134 1 7417 1 7641 1 8168 1 8612 1 902s 1 9410 1 9774 2 0:20 2 0450 Sh 2 02 S2 02 102 02 152 02 202 02 302 02 40202 502 02 60202 702 02 802 02 90202 H e 0 03743 6 653 6 675 7 tti 7 697 8 186 Su7 9 615 10 552 11 484 12 412 13 337 14 261 15 883 097 983 a M7 63 1879 1 1180 3 1207 0 1232 7 12579 1782 7 13319 1381 3 1431 i last 6 1533 0 1585 2 1638 3 s 0 4344 1 6375 1 6390 1 6731 1 7040 1 7324 1 7590 1 8077 18522 1 8935 19321 1 968S 2 003I 2 0361 SR 4707 9707 I4707 19707 29707 39707 49707 59707 69707 79707 89707 78 e 0 01748 6 205 6 664 7 133 7590 8 039 8 922 9 793 10 ES9 11 S22 12 382 13 240 14 097 0 02 131 4 272 74 1180 6 1206 0 1232 0 12573 1282 2 13316 1381 0 1430 9 1481 5 1532 9 158S 1 1638 2 s 0 4411 1 6316 1 6640 1 6951 1 7237 1 1504 1 7913 4 8439 1 8852 1 9238 8 3603 I 9949 2 0279 Sh 4239 92 39 142 39 192 39 292 39 39239 C J* 592 39 692 39 792 39 892 39 75 e 0 01753 5 814 6 204 6 645 7074 7494 8 320 9 135 lb* 10 750 II S$3 12 355 13855 007 611 e 277 % !!81 9 1705 0 1231 2 12 % 7 1281 7 1331 3 1300 7 1430 7 1481 3 1532 7 1585 0 163s i s 0 4474 1 6260 1 6554 16M8 1 71 % 1 7424 1 7915 18361 1 8114 1 9161 1 9526 19872 2 0702 Sh = superhest. F h = enthalpy. Btu per Ib v = specific volume, cu ft per Ib s = eritropy, Stu per F per Ib _ w
8-cn i Tallie 3. Superhealed Steam-Cenedewed 6/5 in 54t Set IN8e - Decen f ahrenheit (548 fem 01 Watee Steam 350 400 450 500 $58 M IN W W IM llW 12W 1300 feet 8h 3796 8796 137 96 18796 23796 207 % 387 % 40796 54796 487 % 707 96 57% 18796 1907 96 N e 848757 5 471 5 ml 6 218 6 622 7 018 7 408 7 794 0 MO 9 319 le 075 le 429 II SGI 82 331 13 ml 13 429 0820el n 202 15 lis)I 1704 0 1230 5 12 % i 1781 3 13m 2 133s 9 1300 5 1430 5 1481 1 1532 6 1504 9 1638 9 1692 0 1746 4
. t 0 4534 1 6208 1 6473 1 6790 8 7000 1 7349 I Jtel 1 7962 1 8209 1 8702 1 9009 1 9454 1930 2 012. 2 0486 2 0750 Sh 33 74 8374 133 74 18374 233 74 203 74 383 74 403 74 543 74 683 74 783 74 5374 933 74 1983 74
-N e 3 01762 5161 5 445 5 840 6 223 6597 6966 7 330 8 052 8 MS 9 400 10 190 10 0B0 11 004 12 310 13 014
, 0 16 264 h 206 52 1104 2 1203 0 1229 7 1M55 1200 8 130b8 3354 las t 14383 lett e 1532 4 1504 7 1637 9 4601 9 1746 8 s 0 4590 1 6159 1 63 % 1 6716 1 700I 1 7279 1 7532 1 7772 1 8220 1 8634 1 9021 1.9J06 1 9733 28063 2 0379 23687 Sh 29 72 79 ?? 129 72 119 77 229 72 279 72 379 72 479 72 579 72 679?? 779 ?? 079 72 979 72 1079 72 80 s 0 017 % 4 895 512e 5 505 5 869 6 223 6 572 6 917 7 600 8 277 8 950 9 621 10290 le M8 .11625 12 290 (320 281 h 290 69 1885 3 1702 0 1728 9 1754 9 1780 3 1305 4 1330 ? 1300 0 le301 1440 8 15323 8504 6 1631 8 1691 4 1746 7 s 0 4643 16 43 16323 t ha6 1 6940 8 7/12 17%7 1 7707 1 81 % 1 4570 84%7 1 9323 19%9 2 0000 2 0316 2 0619 sh 25 87 75 87 1/587 17587 ??l 87 2587 3h 87 4687 575 87 6587 775 s F 8487 Sn s7 10S a t 95 e 0 01770 4 651 4 045 5 205 5%8 5 889 6 221 6548 71% 7838 8 477 9113 9 747 10 3a0 11 017 11644 1324 th h 294 70 1186 2 8200 9 1228 1 1/54 1 1279 8 1305 0 13799 1379 7 14?9 9 6480 6 1532 1 1584 5 I6J7 7 1691 7 1740 6 s 0 4694 56069 36253 16580 1 6876 1 7149 1 7404 176a5 1 8094 8 8509 I 8897 89/6/ I 9609 I 9940 2 02 % 2 oms Sh 2218 12 18 122 18 172 It 22218 27218 377 58 47218 57288 67218 77218 87788 97288 1072 88 ISO e 0 08774 4 431 4 590 4 935 52% 5 584 5 904 6216 6 433 7443 8 050 8 655 9 258 9 060 10 460 11 060 1327 821 h 298 54 lit? 2 1899 9 1727 4 1253 7 1279 3 1304 6 1329 6 1379 5 1429 7 1480 4 1532 0 1504 4 1637 6 1691 6 1746 5 s 04743 1 6027 I 6187 I 6516 3 6814 1 7068 8 1344 5 1506 I SOM i 4451 3 4439 I 9205 I 9552 iSN3 2 0199 2 0502 5h 18 63 68 63 118 63 164 63 218 63 268 63 368 63 468 63 M8 63 h4 63 76863 86863 968 63 1 % 863 105 e 0 01778 4 231 4 M9 4 690 5 007 5 315 5617 5 915 6 504 7 006 7665 8 241 8 816 9 389 9%1 10 532 (331 371 h 302 24 1188 0 1l98 8 1726 6 1253 1 1778 8 1304 2 1329 2 1379 7 1829 4 1440 3 1531 4 1544 2 1637 5 1691 5 1746 4 s 0 4190 8 5988 3 6122 1 6455 I 6755 l 7031 1 1784 1 7530 1 796I I 3396 I 8785 I 9151 I sete I 9428 2 0145 2 0448 Sh 15 21 6523 Il5 21 16521 215 21 26521 M5 21 % 5 23 M521 66521 M528 865 21 965 21 1065 21 lie 0 01782 4 044 4349 4 468 4 712 5 068 5 357 5 642 6 205 6 761 7 314 7865 8 413 8 961 9 507 10 053 (334 196 h 305 80 1108 9 Ill7 7 1275 8 1752 5 1278 3 1303 8 1328 9 1379 0 1429 2 14a01 8531 7 1584 l 1637 4 16*I 4 1746 4 s 0 4834 15%0 I 6061 8 6396 4 6698 1 6975 1 7233 1 1476 1 1928 I 8344 I 4732 1 9099 1.9*46 8 9777 2 0093 2 0397 -
Sh Il 92 El 92 Ill92 161 92 211 92 261 92 361 92 46892 M192 Gol 92 761 92 861 92 96192 1061 92 115 e 0 01785 3 881 3 957 4 265 4 558 4 841 5 119 5 392 5 932 6465 6 964 7 521 8 086 8 570 9 093 9 6t5 (338 081 h 309 25 1189 6 11 % 7 1225 0 1251 8 12779 1303 3 1328 6 13787 1429 0 1479 9 1531 6 1584 0 1637 2 1691 4 17463 s 0 4877 I 5913 1 6001 I 6340 I h44 1 6922 1 2181 1 7425 8 1877 I 8294 I 8682 1 9049 I 9396 I 9727 2 0044 2 0347 4 e *
- Sh 8 73 58 73 10813 358 73 208 13 ;258 13 358 73 458 73 558 73 65873 758 73 858 73 958 73 1058 13 120 e 0 01789 37275 3 7815 40786 4 3610 46341 4 9009 51637 5 6813 61978 6 7006 7 2060 7 7096 8 2119 8 7830 92134 434! 2 1s a. 312 $8 1190 4 li9i6 1224 1 1251 2 12774 1302 9 8328 2 1378 4 1828 8 14198 1531 4 1583 9 I637I 149f 3 17462 s 04919 I 5879 3 5943 1 6286 I 6592 1 6812 i FlJ2 1 7376 I 7829 I 82 % I 8635 1 9001 19349 I 9680 1 99 % 2 0300 sh 2 67 5267 10267 15267 202 67 25267 35267 45267 55267 65267 752 67 852 67 952 67 1052 67 130 e 0 01796 34%4 3 4699 3 7489 4 0129 4 2672 4 5151 4 7589 52384 5 7tle 61814 6 6486 7 1140 75781 8 0413 8 5033 1347 331 h 318 95 alti ? !!93 4 1222 5 1249 9 1276 4 1302 1 1327 5 1377 9 1428 4 1879 4 1531 1 158J 6 16M 9 1691 f 17468 s 0 4998 1 5813 1 5833 I 6182 1 6493 1 6775 1 1037 1 7283 3 7737 I 8155 1 8545 I 8911 1 9259 1 1591 19907 2 0211 Sh 46 % % 96 146 % 1 % 96 246 % 346 % 446 96 546 96 646 96 744 % 446 96 946 % 1046 %
I48
- 0 01803 3 2190 3 4663 3 7143 3 9526 41844 4 4119 4 8588 52995 5 7364 61709 660M 70349 74652 7 8946 0 53 046 h 324 96 1193 0 1220 8 1248 7 1275 3 1301 3 1326 8 13774 1428 0 14791 1530 8 15834 1636 7 1690 9 1745 9 s 0 5071 1 5752 16085 I 6400 1 6686 16949 ' I Fl% 1 7652 3 8071 I 8461 1 8828 1 9176 I 9508 1 9825 2 0129
% 4:' 4: ' ..! 5' 19!s7 24157 14:57 44157 541 57 641 57 74157 leal t ? ci - :04;*; *'
158 e OWmW JL
- 2. 4 343 * !W 4% 4 !!!2 4 5244 4 442i 5 JS07 57%4 1510 46 16i7 pall fIA%
%4 wi/ ehi 17a 7 F.m a t t 14h ;! +. :):41 : 4's ..'4 lW% 13.4 1 l }'g g 14776 1478 8 s OST ;5W ; 50% i fal a 1 %0 ' 16E ? I Tib 1 1573 1 1997 1 8!83 10751 1 9099 194 1 i 's :Ja JM Sn M 45 hn 45 13645 18645 23645 336 45 43645 536 45 6M 45 73645 836 45 9ti as 10g as 168 e 0 01815 2 83 % 30%0 1 2/88 3 441) 36469 3 8480 4 2420 4 62*5 5 0132 5 3945 5 7741 61522 65'9s 6 ecss M t 5$s n 336 07 !!9S 1 1711 4 !?4* 0 2'33 1799 6 1325 4 1376 4 1477? 14784 1530 3 1582 9 1616 3 1640 % 17456 s 0 5206 15 % 159M 1 623i 1 652? 1 6?90 1 7039 1 74*9 1 7919 1 8310 1 8678 1 9027 19h9 19C6 199a0 Sa 31 58 41 48 13158 181 58 231 58 331 $$ 43158 SJI 58 631 58 731 58 831 58 9Ji58 1031 58 1 78 e 0 01821 26738 2 8162 3 0288 32306 34255 J 6158 3 9879 4 3536 47155 50749 54325 5 7888 6 1440 6 4983 rM842; h 341 24 1196 0 1215 6 1244 7 1272 2 1794 8 1324 7 1375 8 1426 8 1478 0 1530 0 1542 6 1636 3 1690 4 17454 s 0 5269 1 559I I 5823 1 6152 1 6447 16717 16%8 1 7428 1 7850 1 8241 4 4610 1 8959 I 9291 1 9608 l 9913 Sh 26 92 76 92 12692 176 92 226 92 326 92 42492 52692 626 92 126 92 826 92 92692 1026 92 140 e 0 01827 2 5312 2 6474 2 8508 3 0433 3 2286 34093 3 7621 4 1084 4 4508 4 7907 5 1289 5 4657 5 8014 elm 3 1373 08i n 344 19 11 % 9 1713 8 1243 4 1271 2 1797 9 1324 0 1375 3 1426 3 14777 1529 7 1582 4 (6M 9 1690 2 1745 3 s 05328 1 5543 1 5743 1 6078 4 6376 I % 47 1 4900 I 7362 1 7784 I till I 8545 1 8494 1 9227 8 9545 8 9849 Sh 2247 7247 12247 I7247 22247 32247 42247 52247 62247 72247 82? 47 92247 102? 47 198 e 0 01433 2 4030 24%I 2 6915 2 8756 3 0525 3 2246 3 5601 3 8889 4 2140 4 5365 4 8572 517% 54989 5 0124 0 27 531 h 350 94 !!97 6 1212 0 1242 0 1270 1 12971 1323 3 1374 8 1425 9 14774 1529 4 1582 1 16M 7 1690 0 17451 s 0 5344 1 5499 I 5667 1 6006, t 6307 16581 1 6835 I ??99 1 7722 I SIIS I 8484 1 8834 I 91 % i 9484 1 9789 sh 18 70 68 20 118 /0 168 20 218 20 318 20 418 20 518 20 61820 718 20 818 20 918 20 1018 20 In v 0 01839 2 2873 23598 2 5480 2 7747 2 8919 3 0583 3 3783 36915 4 0004 4 3077 4 6128 49165 5 2191 5 5209 (381 800 h 355 51 !!983 1210 1 1240 6 I?69 0 12 % 2 13226 1174 3 1425 5 1417 0 1529 I 1581 9 16 M 4 1689 4 1745 0 s 0 5438 I 5454 1 5593 1 5914 1 6?42 1 6518 1 6773 1 7239 I7%3 1 8057 I 8426 1 8776 I 9109 89427 8 9732 Sh = Superheat,I h = enthalpy Stu per Ib v = Specific volume cu ft per Ib 5 = entropy, Stu per F per Ib q m
4 5 Table 3. Superheated Steam-Conthe6#ed o I n' $at Set femoeesture-Derees Faheenheit (Set Tomt watee Steam 400 450 SN Ste IN FW W M8 1000 Ilm 1200 1300 less 1500
& 18 89 64 09 114 09 164 09 214 09 314 09 and G & loos 11409 564 09 91409 10t4 09 1114 09 800 e telted 2 1822 22364 2 4101 25NO 27984 2 9578 3 2137 3 51b 39130 I203 2 1224 1 1256 5 1296 3 1314 5 1368 4 14?0 9 1473 2 1575 9 1579 2 1633 1 16878 1743 3 17994 s 0 5920 1 5076 1 5311 1 5657 1 5960 1 6233 1 6719 1 7153 1 7553 1 7927 1 8283 18(Il 189M 19241 1953f.
Sa 26 69 16 69 12669 17669 21669 376 69 476 69 576 69 6?669 77669 876 69 976 69 1076 69 378 = 0 01899 1 4480 1 5207 1 6462 1 7623 1 8725 2 0823 2.2643 24871 26774 2 8708 3 0628 3 M38 5 4438 3 6332 f 423 31s a 400 53 1203 4 1222 5 1255 2 1285 3 1313 7 1367 8 1420 5 1472.9 1525 6 15789 1632 9 16476 1743 1 !?99 3
- s 0 59 % 1 5048 I 5261 8 5612 1 5918 I 6192 1 6680 i Fil6 l 1516 1 7890 1 8243 1 8579 1 8899 ) 9206 I 9530 Sh 2382 73 82 12382 17382 273 82 373 8/ 47382 57387 673 02 773 8? 87382 973 82 1073 82 338 e 0 01903 1 4044 1 4684 1 5915 1 7050 1 8125 2 0;68 2 2132 2 40' s 2 5950 2 7828 2 9697 3 1545 3 3389 3 5227 e42618s b 403 10 1203 6 1220 9 1254 0 1284 4 1313 0 1367 3 1420 0 14725 15M 3 1578 7 1632 1 1687 5 1741 9 1799 2
- 0 5991 1 5021 1.5213 15%8 3 5876 1 6153 1 6643 1 7019 1 7480 1 1855 l 8208 I 4544 I 8864 8 9171 1 9466 Sh 21 01 71 01 12! 01 171 01 27101 371 01 47101 57101 671 01 771 01 871 01 97101 1071 01 3a8 e 0 01908 1 3640 1 4191 1 5399 1 6511 17%1 1 9552 21463 2 3333 2 5175 2 7000 2 88tl 3 0611 32402 3 4106 0428 99 h 406 80 1203 8 1219 2 1252 8 1283 4 1312 2 1366 7 1419 6 1472 2 1525 0 15784 1632 5 16873 1742 8 1799 0 s 0 6026 I 4994 1 5165 1.5525 4 5836 8 6114 1 6606 8 1044 1 7445 1 7820 1 8174 I 8510 1 8431 8 9138 ' I 9432 sh 1827 68 27 168 27 26827 36827 468 27 568 27 668 27 76427 868 27 96827 1064 27 lie v 0 01912 1 3255 1J725 1 4113 '.18 6002271 7028 1 8970 2 0432 2 2652 2 4445 2 6219 2 7980 2 9730 31471 3 3205 (43173 a 40983 12040 1217 5 1251 5 2824 1311 4 1366 2 1419 2 1471 4 1524 7 1578 2 1632 3 1687 1 1742 6 17989 -
s 0 6059 14%8 1 5119 1 5483 h 5797 1 6077 1 6571 1 7009 1 7411 1 7787 1 8141 1 8477 1 8798 1 9105 1 9400 Sh 1559 6559 115 59 :65 59 265 59 365 59 46559 56559 665 59 765 59 06559 965 59 1065 59 3e8 = 0 01917 12891 1 3285 1 4454 15521 .5525 1 8421 2 0237 2 2009 2 3755 2 5482 2 71 % 2 8894 3 0592 32279 4434 419 h 412 81 1204 1 1215 8 1250 3 1281 5 310 6 1365 6 1418 7 1471 5 1524 4 1577 9 1632 1 1686 9 1742 5 1798 8 s 0 6092 34943 1.5073 1 5441 1 5758 l . 6040 16536 I 6976 I 7379 I754 I 8109 1 8445 1 8766 1 9073 1 9368
$h 10 39 60 39 110 39 60 39 26039 360 39 460 39 560 39 860 39 760 39 060 39 960 39 1060 39 3EB e 0 01925 12218 12472 1 3606 1 4635 5%8 1 7410 1 9139 2 0825 22484 2 4t?4 2540 2 7366 2 0973 3 0572 1439 611 h 418 59 1204 4 1212 4 1247 7 1279 5 309 0 1364 5 1417 9 1810 8 15230 15774 1631 6 1686 5 1747 2 1798 5 s 0 61 % i 4894 1 4982 8 5360 1.5683 .5969 8.6470 1 6918 8 1315 1 7692 1 8047 I 8344 88705 4 9012 1 9307 Sh = superbe8t. F h = enthalpy. Btu per Ib v = specific v0lume. tu ft per lb s = entr0py, Btu per I per Ib G
- r 8
U Tetple 3. Super 90eeted Sleem-CenWeared q A6s Press W$ein $41 Sat MD"aNtMgWalweaheit ($81. lemp) lifatet $le&#n 830 $N $$$ $N $$$ )N W W SW IIN l)N IM l4N 1$N Sh 5 40 55 40 105 40 ISS40 205 40 755 40 355 40 455 40 555 40 655 40 5540 8 % 40 9 % 40 10 % 40 W e 0 01934 1 8610 13738 12841 1 3836 14763 1 % 46 I W99 1 8151 1 9759 7 1339 2 7981 7 4450 25907 7 7515 p goj 7 v 4888Mi b 42417 1704 6 I?o8 8 1245 l 1777 5 1307 4 1335 9 83634 1417 0 14701 1573 3 1575 9 1631 2 1686 7 4741 9 11987 s 0 til7 I4847 1 4894 4 5287 I MI1 1 5901 16163 3 6406 I 6850 1 7255 1 7637 5 7988 8 8325 1 8647 8 99 % I 9750
$h 60 50 60 100 60 150 60 200 60 250 60 350 60 450 60 % 0 60 650 60 750 Gil the to 9bo 60 1050 60 W e 8 01942 1 1957 1 1078 1 2144 1 3:13 4 4007 1 48 % I M16 I 1758 8 8795 2 0304 71795 2 3273 2 4739 2 6196 37647 M4841 h 429 % 1204 7 1205 7 1247 4 1775 4 1305 8 1334 5 1367 3 la16 7 1869 4 1572 7 8576 4 1630 8 lesh 4 1741 6 1798 0 s 0 6276 8 4807 14808 3 5206 1 5547 i $835 1 6300 16345 16791 3 7197 1 1575 1 7937 I 8769 I 8591 1 8899 8 9195 Sh 4597 9597 14597 195 97 74557 345 97 44597 54597 64597 74597 44597 94597 1045 97 448 e 0 01950 10%4 11517 1 7454 1 3319 I 4138 ! a9?t 1 945 1 7918 19363 70790 77703 7 3605 7 4998 7 6384 1454 031 h 434 17 !?04 8 1739 7 1773 4 1304 y 1333 7 IMII I415 3 1468 7 15?? I 1575 9 1630 4 1685 5 1741 7 17977 s 0 6337 64759 I 5132 1 5474 1 5772 1 6040 1 62 % 1 6734 1 7147 8 1571 1 1878 1 8716 1898 88847 8 9141 9 41 50 91 50 141 50 191 50 741 50 34150 441 50 54150 Mt 50 741 50 841 50 941 50 1041 50 488 s 0 01959 1 0097 1 0939 I l85? I 7691 1 348? I 4747 I 5703 1 71I7 I 8504 1 9817 7 I??6 7 7569 7 3903 7 $?30 1454 589 h 439 83 1204 8 !?M 9 !? 71 3 1302 5 13318 1360 0 leis e 1468 & 1521 5 1575 4 1429 9 1685 8 17974 s 06387 14718 1 5060 1 5409 1 5711 1 5987 8 6230 l H80 1 7089 1 7469 1 7826 18165 1 8488 1740 88797 9 ' 1 9093 sh 3718 8718 13718 18718 73718~ 33718 43718 537la 63718 73718 83718 93718 103718 W e 0 01 % 7 0 9668 1 0409 1 1300 1 7315 1 2881 1 3615 1 5073 56384 1 7716 4 9030 2 03JC 7 I619 2 2900 7 4173 M62871 4 444 ?$ B204 8 1234 1 !?69 I 1300 8 1330 5 1358 8 1413 6 1467 3 1520 9 1574 9 1629 5 1644 7 8740 6 87972 s 0 6439 I 4677 1 4 *'10 1 5346 i M52 1 5925 1 6176 i H28 1 1038 1 7419 1 7777 I 8116 I 8439 18748 I 9045
% 32 99 82 99 132 99 187 99 237 99 337 99 43799 532 99 437 99 732 99 83299 93299 1032 99 is e 0 01975 09??6 0 9919 19791 1 1544 1 7377 1 3037 14397 1 5708 16e97 1 87 % 1 9507 7 0746 7 1977 7 3700 1467 01) h 449 52 1204 7 1231 7 1267 0 129s i 1329 1 13577 idly 7 1466 6 1520 3 1574 4 1679 I 1644 4 1740 3 1796 9 s 0 6490 14639 I 4921 1 5284 a 55% 1 5871 16823 1 6578 I 6990 1 1378 1 7730 t 8069 4 4393 1 8702 1 8998
$h 7893 78 93 2893 1893 22893 32893 42893 52493 6789) 72893 878 93 92893 1028 93 818 e 0 01982 0 8914 0 9466 1 0371 .1094 'l886 12504 1 3819 1 5085 1 6323 1 7542 8 8746 1 9940 2 3115 2 2307 -
M11.071 h 454 18 1204 5 1278 3 1764 8 2974 327 7 1356 5 1414 8 1465 9 1519 7 1573 9 1678 7 1684 0 1740 0 1796 7 s 0 6540 1 4601 1 4853 1 5223 $539 I5818 8 6077 I 6530 1 6943 I 7325 1 7684 I 8024 3 8348 8 8657 I 8954 h 74 99 74 99 174 99 174 99 77499 374 99 474 99 574 99 674 99 124 99 824 99 9?4 99 1074 99 548 e 0 01990 0 8577 0 9045 0 5884 i M40 1 1342 1 7010 1 3784 14508 1 5704 56840 1 8042 1 9193 703 % 714FI 6415 01 h 458 71 1204 4 1725 3 1262 5 1295 7 13?6 3 1355 3 1410 9 1865 1 1519 1 1573 4 1678 2 1683 6 1739 7 11964 s 06587 14565 44186 1 5164 1 5483 1 5767 6 6023 1 6483 1 6897 1 7280 1 7640 1 1981 1 8305 1 8615 1 8911
.5h ?!16 11 16 121 16 11116 221 16 321 16 42116 52116 62116 721 16 821 16 921 16 1071 16 188 e 0 01998 0 8264 0 8653 0 9479 10217 1 0902 1 1552 1 7787 8 3972 1 5129 i 6?66 1 7388 i 8500 1 9603 70699 1878 841 h 46314 1204 7 1222 7 1260 3 17939 1324 9 1354 7 1410 0 1864 4 1518 6 1572 9 1677 8 1643 3 1739 4 87 % i s 0 6634 8 4529 84720 t $106 1 5431 15717 I 5975 1 6438 16853 5 7237 I 7598 I 1939 I 8763 1 8573 1 8870 9 1743 6743 11743 16743 73743 3t?43 off43 51743 61743 73743 81743 91743 101743 W v 0 02006 0 7971 0 8287 0 9100 0 9424 1 0492 1 1125 17324 1 3473 1 4593 a S69J 1 6780 1 7855 1 8921 11980 4482 571 # 46147 1203 9 1719 3 1258 0 1292 1 1323 4 1313 0 1409 2 1463 7 1518 0 1572 4 1627 4 16419 1739 1 1795 9 s 0 6679 I 4495 1 4654 1 5049 I 5380 15%8 1 5929 I 6394 168tl I 71 % i 1556 1 78'8 8 8223 I 8533 1 8831 5h 13 80 6380 ll3 8r 18380 2 380 313 80 41380 51380 613 80 71380 81380 913 8" 1013 M 888 . 0 0:011 07697 C N4 OW 0% 1 060? I r26 Ilts 130cs 1 4043 1 5160 1 6261 17N 18?a4 1930e Iy+
e486 20' n 4 71 'O 1203 7 1, N s 7. e I:( f - , Up isp lam 15:74 157i s K?! O Iw t INm 5 0 6723 1 4461 : 4N .em i U:3 i SG lW4 1Eh I tift 9 I lib. I 15 G 1 7859 1 4184 e =N ImM Sh 5.i %!! 10t 11 1 % 11 V l! 305 11 403ll M it 6m il 10% I1 s10$ 11 Fa ll 10M !t 658 . 0 0?O37 0 7044 0 717J 07%4 OMM c e?34 ofem 109/v 11%9 129 N eJ%9 14944 15%>+ l t se4 1 /si t 64%4 89 a 441 89 !?02 8 12076 1144 6 1281 7 1314 1 134* 7 14 ) 0 1461 7 1515 9 1570 7 16?S 9 1681 6 17 w o 1794 9 s 1 6828 14381 14430 148 e ! $207 i %07 1 5775 1 6249 1 M71 1 7059 1 74?? I 71V I 80*J l 2403 1 Col 58 si 92 90 9? 146 9? 1 % 92 296 92 3% 9? 49t 97 5% 9? 6%9? 79:9' 596 Sc 9* 9J 788 o 0 0?050 0 65 % 07??1 0 7928 0 8520 0 9W 1 010: 1 1078 1 2023 1794p 1 343s 14757 1 % 47 1 6', h* (503 08; A 49160 1701 8 1243 4 128a 0 1314 6 1345 6 14c3 7 1459 4 1514 4 IS69 4 1624 8 1680 7 1737 2 1794 3 s 0 6978 8 4304 14726 1 5090 1 $399 I 5673 1 6154 I 6580 I 6970 1 7335 8 1679 I 8006 I 8318 I 8617 SR 39 16 8916 139 16 18916 78916 38916 48916 58916 68916 78916 889 16 989 16 758 e 0 07069 0 6095 0 M 76 0 7313 0 7882 0 8409 0 9386 3 0306 i 1195 12063 1 7916 83759 14597 I $419 6 10 841 h 50089 1200 7 1236 9 1276 1 1310 7 1342 5 1401 5 I4576 1512 9 1%82 1623 8 1679 8 1736 4 17936 s 0 7022 3 4232 l 4598 14977 1 5296 1 5577 16065 3 6494 56886 8 1252 81M8 8 1926 8 8239 I 4538 Sh 31 79 41 79 131 79 II! 79 281 79 381 79 481 79 581 79 681 79 781 79 88e 79 381 79 M e 0 02087 0 M90 0 615; 06774 0 7123 0 7828 08759 0 % 31 1 0470 18289 8 2093 17885 13M9 1 4446 6 18 211 h 509 81 1899 4 1230 1 1271 1 1306 8 1339 3 83 % I 1455 8 1511 4 15M 9 1622 7 16789 1735 7 1792 9 s 0 2.118 I4163 1 44?? I 48e9 I 5198 I 5444 15980 1 6413 16801 1 7125 1 1522 8 7851 3 8164 4 8464 sh 24 16 74 76 12476 174 76 274 76 374 16 474 76 57476 674 76 774 76 8'44 914 76 Sie = 0 02105 0 5330 0 %83 0 6796 0 6829 0 7315 0 8205 0 9034 0 9830 1 0606 1 1366 5 2115 1 28 % 1 3548 621241 h 51840 !!98 0 1223 0 1265 9 1302 8 13M O 1396 8 1454 0 15:0 0 1%57 1621 6 1678 0 1734 9 17923 s 07197 1 4096 14347 I 4763 1 5102 1 53 % i $899 i 6336 1 6733 8 1802 8 7450 1 7780 1 8094 8 8J95 Sh 18 05 6805 118 05 168 05 268 05 368 05 46805 % I 05 E8 05 768 05 864 05 968 05 W8 e 0 C7123 0 5009 0 5263 0 5869 0 6388 0 6858 0 7713 0 8504 0 9267 0 9998 1 9770 1 1430 1 7131 1 7875 1531 951 # $26 70 11 % 4 1215 5 1760 6 4798 6 1332 7 1394 4 145? ? 1508 5 1564 4 1620 6 14771 1734 1 17916 s 0 1279 I 4032 1 4223 14659 I 5010 1 5311 3 5822 4 6263 I6M2 1 1033 1 7382 8 7783 I 8028 I 83?9 a Sh = superhest. f h = enthalpy Blu per Ib v = specific v0 fume. cu f t per Ib s entropy. Biu per F per Ib M s _ ___ __ . --
4 Table 3. Supe 7heele41 Sleem-Continered Ans Pms 1 % tt/5g la 54t $,1 Impedw - De8msIawnet , 15at feme) wale sledm 550 SSB Sie 700 790 000 NO IIS 1000 1100 1300 1300 1800 1900 1 Sh Il 61 61 61 Ill 61 161 61 til el Mt 61 311 61 361 61 est 61 MI 61 est 61 MI El 5168 961 61 ERB e 0 tiles e4721 0 48e3 esees eS993 e M49 eGaia e 7272 0 7666 0 0830 0 8753 89e% i e142 I e017 114e4 12 43 1 S. W h S34 74 1994 7 17076 12 % i lite 4 1329 3 1361 S IM2e 1471S tote 3 1907 9 1963 2 1619 5 1676 2 1733 3 17910 s 0 7368 I M70 l 4094 14%7 1 4923 4 5228 I $100 85748 1 5977 4 6193 i H95 8 6967 1 7317 8 7649 8 7965 4 8267
$h 542 % 42 105A2 IM 42 205 42 2 % 42, 305 42 3 % 42 455 42 % S42 66542 7%of 5542 9%42 tem e 0 e7859 0 4460 04Sn 05837 0 M36 060e0 0 64e9 e6e75 a1745 'o re03 0 8295 esete e9622 ieats Iese I t$29 6 44 301 t $42 % 1892 9 !!99 3 4249 3 1290 3 1325 9 1350 7 13eD 6 1419 4 1448 5 195 4 1561 9 lol84 1675 3 1732 5 1790 3 s 8 7434, 8 3910 IJ973 1 4457 14633 4 5149 I 5426 13677 8DNS l SIM IGNS Isul 1.2256 I Flat iFW5 I e207 h 4987 9947 14947 19947 24947 29947 34947 449 47 54947 64947 74947 esta? 949 47 les e 0 02177 e 4727 0 4821' 0 5312 0 5745 0 6142 06 SIS 06877 0 1216 07 ell 0 0524 0 9151 69767 80U3 1 0973 6 50 531 h M0 ll 1891 0 1743 4 1285 7 13M 4 83 % 8 1387 2 1417 3 1446 6 1503 9 IM07 1617 4 1674 4 1733 4 1789 6 s 0 407 4 3451 14358 84748 4 5072 ISM 4 4 5408 I 5442 14062 3 6469 I 6445 I 7197 i M31 17N4 5 Sill Sh 43 72 1372 14372 193 72 243 72 29372 34372 443 72 543 72 64372 74172 64372 943 72 lie v 0 021 % e 4006 0 4534 05017 0 5440 0 5826 0618e 06533 0 686S 0 7505 0 8123 0 8123 0 9313 0 9094 1 0468 6 % 283 h %7% 1189 1 1237 3 1281 2 8318 8 Init 1384 7 1415 2 1444 7 IS02 4 ISM 4 ;616 3 1673 5 1731 0 1709 0 s 0 7578 13794 1 4259 1444 1 4996 1 5264 1592 1 5779 1 6000 1 6410 46787 1 7141 17475 17793 1 8097 Sh 39 18 9918 13918 189 18 23918 20914 339 14 43918 53918 63918 FM 18 83918 939 18 1398 e 0 02214 0 3807 04763 0 4746 0 5162 0 % 38 0 5889 0 6723 06w4 0 7161 0 7754 0 0332 0 8099 0 94 % 1 0007 6 61 821 h % 4 76 Il87 0 1230 9 4776 6 1315 2 4349 9 1382 2 1483 0 1442 8 1500 9 4%81 I615 2 1672 6 1730 2 17843 s 07647 1 3738 8 4160 1 4582 84923 8 5216 1 5478 1.5717 1 5941 1 6353 16732 4 7007 1 7422 17748 1 8045 Sh 32 81 8281 IN SI 18281 232 81 282 81 332 81 432 81 SM 81 632 81 732 81 832 81 93281 ties e 0 02237 0 3624 0 4016 04497 04905 0 5273 O MIS O H39 06MO 06m$ 0 1418 0 7974 O SSIS 0 90 % 0 %e4 067 191 h $71 SS 1184 8 t224 2 1271 8 13ll $ IM69 1379 7 1410 8 1440 9 14994 l%69 1614 2 1671 6 1729 4 17876 6 0 7714 8 3683 1 4068 14501 14851 1 5150 I $415 1 5658 I Se83 1 6290 I M19 1163) 1 7378 8 7691 1 1996 5h 22 58 ?? SS 122 SS 172 58 222 54 27254 322 54 422 58 522 S4 622 54 722 54 822 54 92254 83 e 0 02269 0 3299 0 3570 0 4052 0 4451 0 4804 0 5129 0 5436 0 5729 06207 0 6822 07MI 0 7e47 04MS 0 8sM 68421 h 58% 58 !!80 7 1209 9 1261 9 1303 9 1340 8 1374 6 1406 4 1437 1 1896 3 Ind3 1612 0 fue8 1727 9 I796 3 s B1943 13577 1 3860 1 4340 14713 1.5022 15296 1 5S44 15H3 15194 1 6578 1 6937 11275 1 7596 1 7902
~
Sh 1293 6293 11293 162 93 212 93 26293 312 93 41293 512 93 61293 712 93 81293 912 93 gag e 0 02307. 0 3018 0 3176 03H7 0 4059 0 4400 04712 8 Sed 4 5282 0SW9 0 6311 0 6798 0 7272 0 7737 0 8195 6 47 071 a $90 83 8875 3 11941 1251 4 12 % I 13M S 8369 3 1402 0 1433 2 14912 a%I4 16m t lute 1726 3 IF8S O s 0198 8 3414 i M52 I 4181 1 4575 14900 I $182 1 $436 1 5670 1 6096 6 6e64 1 6645 I 7185 1 7304 1181$
. . e e B
Sn 3 80 $3 83 103 80 t$3 80. 203 to 253 to 303 80 403 Sw 503 80 6C180 70380 803 80 90300 1988 e 0 02346 0 2772 028J0 0 3328 03717 0 4049 04350 0 4629 0 4894 0 5394 OSM9 06327 0 6773 0 7210 0 7639 6 96 203 a 61164 1170 8 1176 3 1240 7 1287 9 1328 0 1364 0 13974 14292 8490 1 15492 1607 7 IH62 1724 8 17837
*s 0 804S I 3373 1 3431 3 4022 1 4443 1 4182 L 5073 I 5333 1 5572 16004 1 6:95 I 6759 1 1101 1 7425 1 7734
$a le e 0 02387 0 25 %
4513 9513 14513 19513 24113 29513 395 ti 49543 595 1) 69513 79513 8% 3 0 3026 0 3415 0 3741 0 4032 04301 04%S O S031 0 5482 0 5915 0 6336 0 6748 0 7153 t604 til n 424 20 1164 5 1228 3 12794 1321 4 1358 5 1392 4 1425 2 64859 (546 6 160S6 lud3 4723 2 1181 3 s 0 8199 1 3274 1 3861 14312 34M7 8 8968 1 5235 1 5478 I Stil I 6312 I 6678 l 1022 11347 8 1657 Sh 36 87 8687 13647 186 87 23687 28687 306 87 46687 54687 684 87 786 87 48687 lie e 0 02428 0 2361 02754 03147 0 3464 0 3751 0 4011 0 47 % 04711 0 5140 05H2 0 59S1 06341 0 6774 4613 136 h 63645 1158 6 1215 3 1270 5 1314 5 In?9 138s i 1421 2 1483 8 1544 0 8603 4 1825 1721 7 1781 0 1 0 8309 1 3176 1 3657 14183 14%% I 4 86 ? 1 5140 15388 I S833 1 6232 1 6601 16947 1 7274 7t85
$* 28 9P 18 .P I?m u I'e = 729 S8 278 98 378 % 478 # SFS 96 6?S 4 !?n h a 'e %
1800 = 0 0> 4 0 02:8e 07%$ 02w Ort O NO 03's? 0 3988 0 4426 0 44
- 0 52n O Sec a u S4s > W 42
.62 0
- 648 49 115' )
s O tti ? 1 307S i?? ? la:1 1367 4 l ia 7 2 1381 3 1417 1 1483 6 1914 1601 2 ih07 190i 17N 7 i 3S26 1 4054 1 4446 1 4'68 15G43 15302 1 57 % 1 61 % IWS 16476 i 7?f4 I 1%Iti 5a 21 44 71 44 !?! 44 !?! 44 !?! 44 27844 37144 47144 57144 67144 771 de 871 de itse e 0 02Sif 0 7028 C7Na 0 ?647 0 30ra 0 3276 O M23 0 1744 0 4171 04565 0 4940 05303 0M% O ho02 46'8 %;
- MC M 1843 6 118$ 7 125! ) 13Y 7 114! 4 1374 4 1817 9 14774 1984 iS991 16Ss 8 1718 4 4 7't 4 5 b 8S22 I i9a
- I J 146 1 39/S 84138 1 4672 14%0 1 5219 i % 77 I 6384 1 64S8 16808 8 7134 174%I 5h 14 20 64 20 114 20 164 20 214 20 764 20 M4 20 464 20 564 20 H4 20 764 7t 864 70 m = 0 02565 01883 0 2056 0 2448 0 280% 0302 0 3312 0 3534 0 3942 04320 0 4680 05027 0 53E S 0%%
1633 8(3 a 67211 1138 3 1168 3 1240 9 1792 6 1335 4 1373 5 1408 7 1474 l ISM 7 15 % 9 1657 0 1717 0 17711 s 0 862% 1 2881 I 3154 1 3794 1 4231 8 4$78 18874 1 5138 15603 160i4 16391 16743 1 707S l ijst Sa fle v 0 0?615, 01750 7 24 5724 10724 15724 20724 25724 35724 4SF24 % 7 24 6S724 75724 8S7 24 01847 0230e 0 2624 0 2888 0 3123 0 3339 03734 0 4099 0 4445 04778 0 5101 0 5418
- f642764 h 683 79 Il3r $ 1148 5 4229 8 1284 9 1329 3 1368 4 1404 4 1470 9 1533 6 1594 7 16 % 2 17 54 177S 7 s 08727 1 2'80 1 2942 13MI 1 4125 1 4486 34790 1 5960 1 5S32 l 98 8 16327 I M81 1 7014 17J30 Sn
% $0 % 100 55 150 55 200 55 250 55 3$0 55 450 % 55055 650 50 M0 55 8$0 %
21e e 0 02M9 G l627 0 16 % 0 2134 0 2458 02720 02%0 0 3:61 0 3545 03897 0 231 04%I 0 4862 O S16% 6e949 h 69546 1122 2 Ilij t 1218 0 1276 8 1323 1 1363 3 14000 14676 1530 9 IS92 5 1653 3 17 39 17744 s 0 8428 12676 1 2691 1 3523 14020 14395 84704 44944 1 5463 1 $883 3 6264 i H22 169% i 1273 Sa W e 0 02727 01513 4411 94 11 144 11 1941t 244 18 344 18 444 11 544 11 644 tl 744 tl 844 11 P '975 02305 02%6 0 2793 0 7999 0 3372 0 3714 0 40M 04344 0 4643 0 4935 4 % 8 96 h 70718 1113 2 120S 3 1264 4 13I6 7 1358 1 1395 7 1642 1520 3 1590 3 165t $ 1717 3 17738 s 0 8929 12%9 1 3381 13914 14305 14628 84910 1 5397 8 5821 14207 16$65 t 6901 i 1219
$h = superhett, F h - enthalpy, Blu per lb v = specific volume, cu ft per Ib $ = entropy, Blu per F per Ib y
A MASTER C,0?Y y. U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: HATCH 182 REACTOR TYPE: BWR-GE4 DATE ADMINISTERED: 85/03/11 EXAMINER: K E BROCKMAN APPLICANT: _________________________ INSTRUCTIONS TO APPLICANT Une separate paper for the answers. Write answers on Points one side only. for each Staple question sheet on top of the answer sheets. question are_ indicated in parentheses after the question. The passins grade requires at least 70% in each category and-1, a final grade of at
'iP hours after least 80%. Examination papers will be picked up the examination starts.
' % OF CATEGORY % OF APPLICANT'S CATEGORY TOTAL SCORE VALUE CATEGORY VALUE ________ ___________________________________
^^ "^
________ 5. THEORY OF NUCLEAR POWER PLANT
...!!!__ _25 __I__00 ___________
OPERATION, FLUIDS, AND 7q .co THERMODYNAMICS ________ 6. PLANT SYSTEMS DESIGN, CONTROL,
. I __ _ i ___________
AND INSTRUMENTATION 20 0 00 PROCEDURES - NORMAL, ABNORMAL, ___I__0 __ ' I__ __'5 _ ___________ ________ 7. EMERGENCY AND RADIOLOGICAL CONTROL ADMINISTRATIVE PROCEDURES, _ I- __ _ I ___________ ________ 8. CONDITIONS, AND LIMITATIONS C^.^^ 100.00 TOTALS ' 79.00 FINAL GRADE _________________% All work done on this examination is my own. I have neither sivon nor received aid.
- EPPL5CdUiI5~555NETUR5~~~~~~~~~~~~~~
l l L._
V THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 5. ggg y QUESTION 5.01 (1.00) Which of the following is NOT a characteristic of Suberitical Multiplication?
- o. The soberitical neutron level is directly proportional to the nautron source strength,
- b. Doubling the indicated count rate by reactivity additions will PCduce the margin to criticality by approximately one-half.
- c. For equal reactivity additions, it takes longer for the new cquilibrium count rate to be reached, as K-eff approaches unity.
- d. If ten (10) notches of rod withdrawal increases the SRM count rote by 10 cps, then twenty (20) notches of rod withdrawal will increase the SRM count rate by 20 cps. ASSUME CONSTANT ROD WORTH.
QUESTION 5 02 (1.00) The change in reactivity associated with a chanSe in K-eff from 0.920 to 1.004 is approximately ... (CHOUSE ONE) O. 0.091
- b. 0.084
- c. 0.087
- d. 0.080 QUESTION 5.03 (1.00)
A ' Periodic NSSS Core Ferformance Log' (P-1) is attached for reference. Which statement is most accurately reflected by this printout?
- c. Maximum LHGR(s) in the core is 12.00 Kw/ft.
- b. Maximum LHGR(s) in the core is 7.69 Kw/ft.
- c. Maximum LHGR(s) in the core is 13.40 Kw/ft.
- d. Maximum LHGR(s) in the core is 9.19 Kw/ft.
l f l I i
4
- g. .
s'. ,
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3
--- isiRR557EKAfH '
a-QUESTION 5.04 (1 00) The condensate subcooling in a condenser operating at 1-PSIA,
'with_a condensate temperature of.95 des F is ... (CHOOSE ONE)
- o. 6.7' des F
- b. 196.7. des F'
- c. 10.7 des F
- d. 120.3 des F QUESTION 5.05 (2.00)
-The attached figure shows a basic closed loop fluid system with its head vs. flow plot (BOLD LINES). The two pumps are identical, variable speed, radial, centrifugal pumps. Pump 1.is initially
. operating _at one-half speed to supply flow to component 1, as shown.
- o. Component 2 is placed into service, thereby increasing the system heat load. Would total; power consumption be less by ...(CHOOSE ONE)
(1) Doubling the speed of Pump 1 (2) Starting Pump 2 at one-half speed (0.5)
- b. Which Pump Curve - A, B, C, or 0 - most accurately shows BOTH PUMPS operatin3 to supply the system flow? (0 54
- c. With only Pump 1 operating at one-half speed - If component 2 were throttled open from its initial position, would the system flow INCREASE, DECREASE, or REMAIN THE SAME? (COMPONENTS 1 a2 ARE IDENTICAL!) (0.5)
- d. Given one operating pump, that is chan3ed to a POSITIVE DISPLACEMENT
. pump. Is the correct Pump Curve to reflect this Curve A, B, C, or D? (0.5)
V
,q' i
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 5. ggggy g-------------------------------------- QUESTION 5.06 (1.50) MATCH the appropriate Thermal Limit (a-c),
- s. Linear Heat Generation Rate (LHGR)
- b. Average Planar Linear Heat Generation Rate (APLHGR) c.-Minimum Critical Power Ratio (MCPR) to each FAILURE MECHANISM AND to each LIMITING CONDITION given below:
FAILURE MECHANISM LIMITING CONDITION F1. Clad melting caused by L1. Coolant transition decay heat a stored heat boiling following a LOCA F2. Clad cracking from the surface L2. Clad plastic strain
-becoming vapor ' blanketed * < 1%
F3. Clad cracking caused by L3. Maximum clad temp-high stress from pellet erature of 2200 des F expansion GUESTION 5.07 (1.00) Which of the following describes the chsnges to the steam that occurs between the inlet and the outlet of a REAL turbine?
- a. Enthalpy DECREASES, Entropy DECREASES, Ovality DECREASES
- b. Enthalpy INCREASES, Entropy INCREASES, Quality INCREASES
- c. Enthalpy CONSTANT , Entropy DECREASES, Quality DECREASES
- d. Enthalpy DECREASES, Entropy INCREASES, Quality DECREASES
5.- THEORY OF. NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5 ___________ -g
, s ..
QUESTION 5 08- (1.00) Given the followin3 Power History:
\eo . --
w=w
% .s w M.) = . . . . . , .
. - g. 6 w . so * * ' ** Sc. '- .. % % i,, . ,
ti m s ( w . . . s) . .. Select the most accurate curve displaying the expected XENON transient. 4.. .
- e. .
- a. [ , , 5 .
o i. Ic so so sc sc. ie se v. % '. %e % w. s. tin a. . .) 4 0%Y u.. . (*W4 4 5 5 5 1 W 3 F i e v 5 5 5 h 00 IO h .$ % 6.o T$ %b % 0. g IO g I Lg I%g *9 g g T %MI (h. *%I e Igunw Xetsmas C. k 8 1 8 I , 5 1 3 5 5 t i 5 ( l 5 5 O O. IS M %$ kO b 49 I. N GP I, kg %o
$ $g %g TtMr (h. s)
Eg... hw -
- d. g g y y 5 5 Y E E E W W
%. %b 44 9 %M %%e T. N ID O. I. bg (, Sg g
@ 09 Tima (w. .si
i
- 5. THEORY Or/ NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6-y g--------------------------------------
00ESTION 5.09- (1.00) Which of the-following accurately describes a benefit of the Control Cell Core (CCC)?
- o. The Capacity Factor is increased due to the elimination of rod pattern exchanges.
- b. Operations are simplified since flux shaping is no longer required.
- c. Thermal Limit margins are increased due to the elimination of all high power fuel bundles,
- d. Fuel reliability has been improved due to the increased PCIONR ramping. rates which have been incorporated.
QUESTION 5.10 (2.50) The attached figure represents a transient that could occur at a BWR. Givent (1) All FW Pumps trip at time T=1.2 min (2) No operator actions occur (3) Recorder Speed = 1 division = 1 minute EXPLAIN the cause(s) of the following recorder indications: a.- Core Flow DECREASE (Point A)
- b. Reactor Pressure INCREASE (Point B)
- c. Level INCREASE (Point C)
- d. Pressure FLUCTUATION (Point D 0 Time 3 - 7 minutas)
- o. Reactor Power DECREASE (Point E)
GUESTION 5 11 (2.50) The attached figure represents a transient that could occur at a BWR. Givent. (1) Both Recirculation Pumps trip at time T = 1 min (2) No operator detions occur (3) Recorder Speed = 1 division = 1 minute EXPLAIN the cause(s) of the following recorder indications:
- a. Core Flow DECREASE (Point A)
- b. Level INCREASE (Point 3)
- c. FW Flow DECREASE (Point C)
- d. Power INCREASE (2.2 - 3.2 minutes - Point D)
- o. Why did Turbine Steam Flow stabilize at approximately 50%?
m-e' THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7 5. y ggggg-------------------------------------- QUESTION. 5.12 (1.00) A reactor. heat balance was performed (by hand) during the 00-08 chift due to the Process Computer being 00C. The GAF's were computed, but the-APRM GAIN ADJUSTMENTS HAVE NOT BEEN MADE. Which of the following statements is TRUE concerning reactor power?
- a. ' If the feedwater temperature used in the heat balance calcu-lation was LOWER than the actual feedwater temperatoget then the actual power is HIGHER than the currently calculated power.
- b. If the reactor recirculation pump heat input used in the heat balance calculation was OMITTED, then the actual power is LOWER than the currently calculated power.
- c. If the steam flow used in the heat balance calculation was LOWER than the actual steam flow, then the actual power is LOWER than the currently calculated power.
- d. If the RWCU return temperature used in the heat balance cal-culation was HIGHER than the actual RWCU return temperature, then the actual power is LOWER than the currently calculated power.
i THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 8 5. y g-------------------------------------- s .c o 5.13 (9 ,44-)
. QUESTION Given! Reactor Power 60%
Core Flow 40% T (Tau) .6 Fuel Type P8n8R Max Flow Rete / 107% Figure: 5.4, 5.5, 5.6 Enclosed
- 'C"0CCC 0"C' (g,o3
.. O'MCP" i:
(1) 1.931 (2) 1. hdd ( .539
- b. If the MCPR Printout from the Process Computer for Rod 29-17 read 1.973, which of the following would be required per Unit 2 Tech Specs?
(1) No Action Required (2) Initiate corrective action within 15 minutes and continue the corrective action so that MCPR is within the applicable limit within 2 hours, or reduce thermal power to < 25% within the - next 4 hours. (3) Initiate corrective action within 15 minutes and continue the corrective action-so that MCPR is within the applicable limit within 4 hours, or reduce thermal power to < 25% within the nent 8 hours. (4) Place the reactor in HOT SHUTDOWN within 2 hours and reduce steam dome pressure to < 785 psis and core flow to < 10% within the next 4 hours. QUESTION 5.14 (1.00) The fission process in a commercial reactor requires the neutrons that are ' born' by' fission to be 'thermalized.' The interaction in the reactor core which is most efficient in thermalizing neutrons for fission occurs with the ...(CHOOSE ONE)
- a. OXYGEN atoms in the water molecules
- b. BORON atoms in the control rods
- c. ZIRCONIUM atoms in the fuel cladding
- d. HYDROGEN atoms in the water molecules s
1 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 9 5. 00ESTION 5.15 ( .50) Answer the following TRUE or FALSE
- With a reactor that is critical, low in the intermediate. range, an EQUAL amount of POSITIVE or NEGATIVE reactivity insertion (e.g. 10E-4 k/k) will produce stable periods of EQUAL MAGNITUDE.
O r i-+--- - v --w-w- --,-w -,- - ----#y -4 +- + -e-- - +-- -- -----m - ~~- - e--+ - -
~l
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 10 e
QUESTION 6.01 , (1.00) The Drywell Pneumatics System is operating in its normal line-up (Mode B).' Pressure' DECREASES (to approximately 100 psis). The
. system will automatically align such that ...(CHOOSE ONE) o.. ...the back-up Nitrogen supply line isolation valve (F001A) will OPEN and the bypass valve (F001B) will CLOSE.
- b. ...the back-up Nitrogen supply line isolation valve (F001A) will OPEN and the bypass valve (F001B) will OPEN.
- c. ...the Essential /Uninterruptable Instrument Air supply line isolation valves (F029 & F053) will OPEN.
'd. ...the Non-essential /Interruptable Instrument Air supply line teclation valves (F036 & F038) will OPEN and the Drywell Pneumatics -Ccapressors will TRIP and ISOLATE.
QUESTION 6.02 (1.00) Given a Low CST Level on Unit 1 AND a High Torus Level on Unit 2. Which one of the following accurately describes the responses of the HPCI and RCIC Systems?
- o. BOTH units' HPCI AND RCIC will auto-swap to Torus Suction.
- b. Unit 2 HPCI AND RCIC will auto-swap to Torus Suction; Unit 1 will auto-swap for HPCI ONLY.
- c. Unit 1 HPCI AND RCIC will auto-swap to Torus Suction; Unit 2 will auto-swap for HPCI ONLY.
- d. BOTH units' HPCI will auto-swap to Torus Suction; RCIC does not swap.
G 1
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 11 6. P y. QUESTION 6.03 (1.00) Given: Unit 2 in control of D/G 'B' D/G *B' Mode Switch in TEST (Surveillance being performed) Electrical distribution NORMAL (Full Power Lineup) D/G *B' is at rated speed and voltage, but not synchronized, when power is lost to 4160 volt Bus 2F. Which of the following accurately describes the system operation?
- a. Bus 2F can be powered by D/G 'B' when the operator takes the Gutput_ Breaker Switch to CLOSE and has the SYNC SCOPE activated.
- b. Bus 2F will be powered by D/G 'B' automatically, after 12 seconds; cppropriate loads will be picked up sequentially.
- c. Bus 2F can not be powered by D/G 'B' while it is in the TEST mode, given these conditions.
- d. Bus.2F can be powered by D/G *B' when the operator resets the Lockout Relay, activates the SYNC SCOPE, and takes the Output Breaker to CLOSE.
QUESTION 6.04 (1.00) The Main Turbine first stage pressure switches provide permissives and/or control signals for several plant functions. Which of the fo11owin3 is NOT one of these control functions? a.- Recirculation Pump RPT breaker trip permissive
- b. RSCS bypass
- c. RWM LPAP
- d. TSV, 10% Closure Scram bypass a
8 a
- 6. . PLANT. SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 12 QUESTION 6.05 (1.00)
The' Recirculation Flow Control System contains a 44% Speed Limiter to control Recirculation pump speed under certain plant conditions. This 44% Limiter ...(CHOOSE ONE)
- c. ...is first activated when total feedwater flow decreases below 20% and a reactor vessel low water level alarm is received.
...is designed to prevent Recirculation pump cavitation by b.
cnsuring adequate Net Positive Suction Head.
- c. ... enables the FWCS to recover reactor vessel water level upon loss of one Reactor Feedwater pump.
- d. ... automatically resets when the initiating signal clears to cnable the operator to restore normal recirculation flow.
QUESTION 6 06 (1.00) The Reactor Water Cleanup System (RWCU) is being operated in the
' Hot Blowdown' mode to control reactor water level. Which one of the following limitations is NOT a valid concern to the operator while controlling blowdown flow rate to the main condenser?
- a. Exceeding the maximum allowable RBCCW System temperature exiting the Non-Regenerative Heat Exchan3er (N9HX).
- b. Exceeding the maximum allowable RWCU system temperature exiting the NRHX.
- c. Exceeding the Pressure setpoint for downstream of the Blowdown FCV.
D. Exceeding the design cooling capacity of the Regenerative Heat Exchanger (RHX). 00ESTION 6.07 (1.00) Which one of the following accurately describes Low-Low Set (LLS) logic, as applied at Plant Hatch?
- a. Lowers BOTH the openin3 and closing setpoints of the LLS valves.
- b. Controls the operation of all relief valves, excepting E and H.
- c. Is activated by a position switch which confirms any SRV opening.
- d. Is applicable to Unit 2 ONLY.
l
. , - - - , . -,. - - . - . . - . ~ , - . - _ _ . . , - , , - , . , . - . - . . - . -
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 13 6. m . d- = QUESTION 6.08 (2.00) ReSarding the Residual Heat Removal (RHR) System while operating
-in the Shutdown Cooling (SDC) Mode:
- o. STATE'why it is necessary to prevent the RHR pump's dischaP3e from (1.0) decreasing below 400 spm.
- b. . LIST 2 ways in which the system will be effected i f reactor (1.0) pressure increases to above 135 psis.
OVESTION 6.09 (2.00) With regard to the Unit 2 HPCI System: O. LIST the two (2) . conditions (including setpoints) which will cutomatically initiate HPCI. (1.0)
- b. For each of the situations listed below, STATE whether HPCI WILL or WILL NOT Automatically Inject into the reactor vessel. (1.0)
NOTE: ASSUME NO OPERATOR ACTIONS; ASSUME ANY FAILED COMPONENTS WERE IN THE FAILED CONDITION AT THE TIME OF THE AUTO INITIATION SIGNAL. (1) The GLAND SEAL EXHAUSTER VACUUM PUMP fails to operate. (2) The MINIMUM FLOW VALVE fails to auto open (stays shut) when - system conditions require it to be open. (3) After decreasing to 50 psis, HPCI Steam Line Pressure increases to 150 psis. (4) After increasins to +60 inches, Reactor Vessel Water Level decreases to -60 inches. 4 0
--w . , - - - ,
. - -- . - , , -, . , . , , ,, , , , .- n-,- - . .-l-, , - , , . , - , , , - - . - -
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 14 4.
~ QUESTION 6.10 (1.00)
The Unit 2 Vital AC Power 120/240 v Distribution Cabinet 2A is normally supplied from 600 v Bus 2D through a Battery Charger and a Static Inverter. If the Static Inverter fails ...(CHOOSE ONE)
- c. ... the 125 vde battery will maintain power to-the Vital AC Ccbinet for up to 6 hours.
- b. ...the power supply can be manually transfered to the alternate 600 v Bus 2C / Vital AC Transformer 2A by depressing a transfer PB.
- c. ...the power supply will automatically transfer to the alternate 600 v Bus 2C / Vital AC Transformer 2A.
- d. ...the power supply can be manually transfered to the alternate 600 v Bus 2C / alternate Static Inverter by depressing a transfer PB.
QUESTION 6.11 (1.00) The, Unit 1 Primary Containment Atmospheric Control System can be used to vent the primary containment under normal operating con-ditions. To do this, the operator must manipulate the key-locked bypass switches. The direct effect of doing this, and the method by which this is done, is to ...(CHOOSE ONE)
- o. ... override the HI MSL PRESSURE ( > 850 psis) isolation signal by HOLDING the bypass switches in the BYPASS position.
- b. ... override the HI MSL PRESSURE ( > 850 psis) and the LOCA isolation signals by HOLDING the bypass switches in the BYPASS position.
- c. ... override the HI KSL PRESSURE ( > 850 psis) isolation signals by PLACING the bypass switches in the BYPASS position.
- d. ... override the HI MSL PRESSURE ( % 850 psis) and the LOCA isolation signals by PLACING the bypass switches in the BYPASS position.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 15 4. QUESTION 6 12 (1.00) Unit 1 is operating at 48% RTP using Reactor Feedwater Pumps 1A cnd 1B. Feedwater Line A is isolated (MOV F006A Shut). With this condition, a flowpath for RWCU ... (CHOOSE ONE)
- a. ...CAN BE MAINTAINED. The RWCU connection to FW Line A is isolated by removing the spool piece between RWCU and the HPCI dischargei RWCU is operated via RCIC and FW Line B.
- b. ...CAN BE MAINTAINED. The RWCU connection to FW Line A is isolated by manually valving shut the connection between RWCU and the HPCI discharge. RWCU is operated via RCIC and FW Line B.
- c. ...CANNOT BE MAINTAINED. The RWCU flow to FW Line A is not isolable since the RWCU to HPCI discharge connection is not valved.
- d. ...CANNOT BE MAINTAINED. RWCU only has a discharge isolation valve on its common discharge header; no FW line can be isolated without securing RWCU.
QUESTION 6.13 (1.00) Which of the following statements correctly describes the protective trip function (s) associated with the Reactor Recirculation pumps / motor generator sets?
- a. The 'EOC-RPT* trip protects the plant from overpressuri=ation transients (e.g. MSIV Closure) by tripping the recirculation pumps, when reactor pressure e::ceeds 1120 psis.
- b. The motor generator field breaker stays closed in most instances when the MG Set drive motor breaker trips, in order to maximi:e coastdown flow.
- c. The two.'EOC-RPT' breakers for each recirculation pump are redundant to the MG Set drive motor breakers, and interrupt power to the MG Set during overpressurization transients.
- d. The reactor recirculation pumps trip on low low reactor vessel water level, to ensure Net Positive Svetion Head (NPSH) requirements are met.
t 6.- PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 16 l
)
GUESTION 6.14 (1 00) s-A reactor startup/ power ascent is in progress with the 'B' IRM failed upscale and in BYPASS. The mode switch has just been taken to 'Run". WHICH one of the fo11owin3 situations /
.ovents will cause a reactor HALF-SCRAM?
- a. APRM Flow Converter (Unit) 'A' sees INOP
- b. APRM 'B' fails DOWNSCALE
- c. One of the 11 valid LPRM inputs to APRM *B' fails DOWNSCALE d.- APRM 'B' Mode Switch is taken to STANDBY r
1 I' t t-l S
i 60 PLANT SYSTEMS DESIGNe CONTROL, AND INSTRUMENTATION PAGE 17 QUESTION 6 15 (1 00! Which of the displays of the indicator lights for ATTS indicate that the system is in its normal operating mode with NO ALARM CONDITIONS Present? (CHOOSE ONE) P:JTE: FIGURES 9.9(3) AND 9.9(6) PROVIDED FOR REFERENCE DISPLAY / COLOR LITE / PANEL (a) (b) (c) (d) TRIP STATUS /MTU ON/ Green OUT ON/ Amber OUT STATUS /MTU ON/ Green ON/ Green OUT On/ Red GROSS FAIL /MTU ON/ Green OUT ON/ Green OUT POWER /P925 ON/ Green ON/ Clear ON/ Red ON/ Green
t
- 4. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 18 QUESTION 6 16 (2.00)
EXPLAIN how reactor vessel level is controlled in the dP Mode during a reactor startup. Include the parameters which are sensed and the plant systems / components controlled. QUESTION 6.17 (1.00) j STATE how (INCREASE, DECREASE, REMAIN THE SAME) Drywell Pressure would be expected to respond to an SRV discharge line vacuum breaker STICKING OPEN durin3 actuation of the SRV. EXPLAIN YOUR CHOICE. l 1
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 19
~~~~R5656[6656A[~C6UTI6[~~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 7.01 (2.00) Procedure HNP-2-1909, ' Inability to Shutdown With Control Rods", Otates that:
- if at any time, either condition b(1) or b(2) exists, and either _____ (a.1) ____ or ____ (a.2) ____ , and if,it is obvious that the reactor cannot be shutdown and, in the judgment of the Shift Supervisor, or in his absence, a licensed operator, a hazard exists to the environs, personnel, or the plant, utili:e the standby liquid control system per HNP-2-1400 ...'
- c. LIST conditions (a.1) and (a.2). (1.0)
- b. LIST conditions b(1) and b(2). (1 0)
QUESTION 7.02 (1.50) Procedure HNP-8008, " Radiation Work Permit', describes three (3) j different types of RWP's which can be issued - REGULAR, ROUTINE, -{ and BLANKET. For the following situations, STATE the most appro- i' priate RWP_to be issued. O. Unit 1 is in an outage and the main turbine is being repaired. A controlled work area, with constant HP coverage, has been established (. ~for the round-the-clock repairs. This should last for several weeks. (0.5) I k
- b. Unit 1 is in an outage and the main turbine requires inspection.
Constant HP coverage will be maintained; the job shou'ld take opproximately 18 hours. (0.5)
- c. Unit 1 is in an outage. Special outage procedures will require routine (once per shift) entries into a Hi Radiation Area for com-ponent inspection. This will be required for the next three (3) months. - (0.5) t L_. .. .. ..
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERCENCY AND PAGE 20
~~~~
~~~~~~~~~~~~~~~~~~~~~~~~
RA656L66E65b"EUNTR6L
-0VESTION '7.03 (1 00)
You are supervising refueling activities on the Refueling Floor and hear the ARM HI RADIATION ALARM. No control rods are currently with-drawn. Per HNP-1903, " Refueling Floor High Radiation', you would contact the Control Room after ...(CHOOSE _ONE)
- c. ...immediately evacuating all personnel involved in fuel handling-octivities to the 130' Health Physics area.
- b. ... reading the ARM level locally and immediately evacuatin3 ALL persor.nel to the 130' Health Physics arear if the level is > 50 mR/hr.
- c. ...immediately evacuating ALL personnel on the refuelin3 floor to the 185' Change area.
- d. ...immediately evacuating those personnel in the vicinity of the clarming ARM.(not the entire R/F Floor) to the 185' Change' Area.
QUESTION 7 04 (1.00) You enter HNP-2-1910, ' Loss of All Plant Service Water', and are unable to restore PSW operation. Subsequent operator actions require you to place Fuel Pool Cooling in operation at maximum flow. This is done to ...(CHOOSE ONE)
- e. ... proside a long-term heat sink for RHRSW via the Fuel Pool Cooling Assist connection.
- b. ... prepare for the high heat load from the impending reactor ehutdown and required fuel unload.
- c. ... provide a long term heat sink for TBCCW.
- d. ... Provide a short term heat sink for RBCCW.
e w
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 21 7.
~~~~
RA65 E 656AL"5 TR6L'~~~~~~~~~~~~~~~~~~~~~~~ QUESTION 7.05 ( .50) CAUTION You enter an area posted with the following sign! gg 2"~"7 nammd,esseea MEEP OUT 1hery,sgu oros As a minimum, how often should you read your pocket dosimeter? GUESTION 7.06 (1.00) Unit 2 is operating at 70% RTPi you notice power start to increase with NO CHANGE in recirculation flow or rod position. You suspect c Loss of Feedwater Heating. Which of the following actions are required / appropriate, per HNP-2-1946?
- a. A 20% reduction in Recire Flow, monitored by Recire Flow Controller os signal variance.
- b. A 20% Power Reduction, using Recire Flow, monitored by APRM's.
- c. Insertion of Shallow Rods, to maintain proper flux shape, prior to reducing Recite Flow.
- d. Insertion of Power Rods, to maintain proper flux shape, prior to reducing Recire Flow.
l 9
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 22
~~~~
RA656L66 CAE~C65TR6E~~~~~~~~~~~~~~~~~~~~~~~~ QUESTION 7.07 (1.00) A. CAUTION in HNP-2-1902, ' Pipe Break Inside Primary Containment', otates that:
'A Pipe Break in the Drywell could result in Reactor Level Reading inaccuracies due to increased temperature.
Refer to Section 'E' ... for erratic correction method before proceeding. Erratic level indication could be due to water in the sensing line flashing to steam.' Using Section 'E', enclosed, and given the following readings: 2T47-R620 192 des F 2T47-R621 228 des F 2B21-604A +26 inches 2B21-604B +23 inches What is the best estimate of Actual Water Level?
- o. +9-1/2 inches
- b. +15 inches
- c. +34 inches
- d. +27-1/2 inches t
QUESTION 7.08 (1.00) Which of the following conditions establishes the reactor in HOT STANDBY, as defined by HNP-2-1015, ' Maintaining Hot Standby Con-
-dition'?
PAPANETER CONDITION (a) /b) (c) (d) Mode' Switch S & HS S & HS S & HS S & HS Coolant Temp > 212 des F > 212 des F > 200 des F > 200 des i
< 1010 psis ' 1010 psig < 1040 psig Rx Pressure < 1040 psig K-eff 1.000 < 1.000 1.000 < 1.000 OUESTION 7.09 (1.00)
Both Recirculation Pumps trip. You place the Mode Switch to SHUTDOWN but are, subsequently, UNSUCCESSFUL in restarting either Recire Pump. COMPLETE THE FOLLOWING: (HNP-2-1932)
' Subsequent to Reactor Shutdown, and without both recir-colation pumps operating, maintain vessel level from (greater than) ____
(a) ____
, to ensure ____(b) ____.
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 23
~~~~R I656E 6 CIE~C6NTR6E~~~~~~~~~~~~~~~~~~~~~~~~
GUESTION 7.10 (1.00) You receive the following annunciator alarm: PONDEX SYSTEM TROUBLE You determine that you have a Condenser tube leak, per HNP-2-1928,
' Condenser Tube Leaks'. Which one of the following accurately describes your Operator Actions?
- c. Confirm demin effluent < 0.1 umho/cm; increase power to maintain conductivity < 2.0 umho/cmi commence a reactor shutdown if con-ductivity > 0.5 unho/cm.
- b. Confirm demin effluent < 1.0 umho/cmi decrease power to naintain conductivity < 2.0 umho/cmi initiate fast shutdown if conductivity becomes > 2.0 umho/cm.
- c. Confirm demin effluent < 1.0 unho/cmi increase power to caintain-conductivity < 2.0 umho/cmi commence normal reactor chutdown if conductivity becomes > 5.0 umho/cm.
- d. Confirm demin effluent < 0.1 umho/cm; decrease power to esintain conductivity < 0 2 umho/cm; initiate fast shutdown if conductivity becomes > 0.2 umho/cm.
GUESTION 7.11 (1.00) Procedure HNP-2-1934, ' Torus Water Temperature Above 95 des F', directs:
'If any point indicates a torus temperature Steater than or equal to 95 des F, initiate torus cooling...' -
Additionally,
' Operator should not initiate torus coolins unless water level.is ___(1) ___ and at a level greater than ___(2) ___.
Which of the following are the MINIMUM requirements for (1) and.(2)?
- a. (1) Stable (2) that required for Natural Circulation
- b. (1) Increasins (2) Top of Active Fuel
- c. (1) Stable (2) 2/3 Core Height
- d. (1) Increasins (2)- Reactor Vessel Zero l
l l l I l 1 i
, , ,.t._ I
. ... , v._,_ _ _ , _ . . - , _ _ . . . _ . -
,1 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 24
- 7. ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R5656L66fCIE~CUNTR6L 'GUESTION 7 12 (2.00)
Place the following procedural steps from HNP-2-1001 into the proper sequence, as they would be performed during an actual reactor plant startup and pressurization according to the procedure:
- o. Stabili:e reactor power with 1-1/2 BPV's open
- b. Start a Mechanical Vacuum Pump
- c. Open the. Steam Seal Feed and Bypass Valves
- d. Establish vessel water reject thru the RWCU System o.. Place a SJAE into service -
- f. Start a Steam Packing Exhauster 9
-Place RCIC in Standby, per HNP-2-1125
- h. Start Reactor Feedwater Pump 2A (or 2B)
QUESTION 7.13 (1.00) Procedure HNP-2-4207, " Transformer Fire', lists three (3) Operator Action Steps for a Startup Auxiliary Transformer fire. Which of the following is NOT a required Operator Action?
- o. Confirm CARDOX system actuated.
- b. Manually start the required D/G's and synchroni:e to the E-bus.
- c. Deenergize the Transformer.
- d. Evaluate the plant conditions for possible shutdown.
QUESTION 7.14 (2.00) Procedure HNP-2-1001, ' Normal Startup*, instructs the operator to' REAC water level select switch (select level Bi level A to be used only when performing maintenance or surveillance NOTE: FIGURE 2.3(2) IS on level B). PROVIDED AS REFERENCE EXPLAIN why. level-B is specified. QUESTION 7.15 (1.00)
' Procedure HNP-2-1437 ' Reactor Recirculation Pump Speed Chan3es', cautions the operator not to start an idle pump unless the other pump is operating at < 50% loop speed.
' EXPLAIN the reason for this procedural CAUTION.
1 l l l
)
.4 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 25
- 7. ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~EA656L665CIEIEIETE6L QUESTION 7.16 (1.00)
Procedure HNP-2-1005, ' Power Changes", states that Unit 2's licensed maximum thermal power for steady state operations is 2436 MwT. EXPLAIN in what instance (s) this maximum power may be exceeded end how this is verified.
'GUESTION 7.17 '(1.00)
Which of the following is NOT required to be immediately verified or executed by the operator in response to a ' Suspected Fuel' Element Failure', Per HNP-2-1930?
- c. Verify the Off sas adsorber bypass valve (F043) CLOSES on an Off-gas Pre-treatment high alarm.
- b. Verify the Off gas stack inlet valve (F057) CLOSES on an Off-gas Post-treatment high-high-high alarm.
- c. Lock out all the Drywell and Reactor Building Sump pumps until analysis can be performed, or the SS's approval.
.d. DO NOT reject any reactor water to the Main Condenser or Radwaste without the SS's approval.
I
- 8. ADMINISTRATIVE-PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 26 QUESTION 8.01 (1.00)
Which of the following scenarios requires application of the Power Transient fuel cladding integrity Safety Limit of the Unit 1 Tech-nical Specifications? o.- Reactor power is at 42% RTPi the main turbine trips due to on EHC malfunctioni the reactor SCRAMS on HIGH PRESSUREi the BPU's control pressure thereafter.
- b. Reactor power is at 70% RTP; a steam leak to the Drywell occurs cnd Drywell pressure rises; the reactor SCRAMS at 1.85 psisi HPCI cuto-actuation does not occur, but manual start is successfull the reactor is brought to a cold shutdown condition.
- c. Reactor is in Start-Up, at 12% RTPi power is increased by rod pulli_ the reactor SCRAMS at 12 5% power, by APRM's; level and pres-cure are maintained by normal systems for the plant status.
- d. The reactor is at 18% RTPi 1-1/2 BPV's are open in preparation for turbine warmupi controller failure reduces pressure to 875 psisi MSIV's closei reactor SCRAMSi level and pressure are maintained by normal systems for the plant status.
QUESTION 8.02 (1.00)
~ Unit 2 is operating at 90% RTP. As part of the normal surveillance program, functional tests of the MSL Radiation Detectors are perf ormed.
(APPLICABLE TS's ARE ENCLOSED FOR REFERENCE) Given that 2011-K603 A tests UNSAT, which of the following is . cost TRUE? (a) Establish a trip condition for the channels fed by K603A within 1 hour, and be in STARTUP with the MSIV's CLOSED within 2 hours, or be in HOT SHUTDOWN within 6 hours. (b") Establish a trip condition for the channels fed by K603A
- within i hour, and be in STARTUP with the MSIV's CLOSED within 2 hours, or be in HOT SHUTDOWN within 6 hours and COLD SHUTDOWN within the next 30 hours.
(c) Establish a trip condition for the channels fed by K603A within 1 hour, but you may continue in Operational Condition 1. (d) Establish a trip condition for the chennels fed by K603A within i hour and be in at least HOT SHUTDOWN within 6 hours and in COLD SHUTDOWN within the following 30 hours.
3 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMI1ATIONS PAGE 27 8. QUESTION. 8 03 ( .50) STATE who can declare the unit / plant to be in an emergency con-dition (classification). NOTE: Identify by Position Title and any special required qual-ifications. QUESTION 8.04 (1.00) Unit 2 Technical Specifications specify the frequency intervals for the performance of Surveillance requirements. This i s accom-
-plished by use of FREQUENCY NOTATION.
COMPLETE the followins Table. (D0 NOT INCLUDE GRACE PERIODS) NOTATION FREGUENCY o) S At least once per _______ hours. b) G At least once per _______ days. c) M At least once per _______ days. d) ___ At least once per 18 months. QUESTION 8.05 (1.50) Unit 2 Technical Specifications define SHUTDOWN MARGIN as...
' Shutdown Marsin shall be the amount of reactivity by which the reactor is soberitical, or would be subcritical from its present condition, assumins...'
LIST the three conditions which complete the definition of SHUT-DOWN MARGIN. y 7 7 , , - - -. -. s-- y n- -
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 28 QUESTION 8.06 (3.00)
- a. The following data was taken on Unit 2 during a single day of operation at Operational Condition 1:
Identified Leakage Unidentified Leakage Shift 1 0400 5020 gal 604 gal 0800 4940 gal 1020 gal Shift 2: 1200 5040 gal 900 gal 1600 5340 gal 1032 gal Shift 3: 2000 5840 sal 1100 gal 2400 4640 gal 1248 gal Indicate;any TS (or other) limit (s) that was(were) exceeded. Justify your answer (s). (2.0) b)- What is the definition of ' Pressure Boundary Leakage?' (1 0) GUESTION 8.07 (1.00) Temporary changes to operating procedures should be minimi=ed. Under which one of the following conditions is a temporary change permitted and warranted, as the proper corrective action?
- e. The addition of a CAUTION is necessary to prevent possible equipment damage.
- b. A correction is required to a valve / electrical lineup.
- c. The plant physical conditions assumed by a procedure are incorrect and prevent its completion as written.
- d. A procedural step is determined to be unnecessary and should be deleted.
I
m 2 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND
- IMITATIONS PAGE 29 8.
QUESTION 8 08 (1 00) Per Administrative Procedure MNT-01-0, " Maintenance Program *, EMERGENCY MAINTENANCE ...(CHOOSE ONE)
- o. ... is maintenance that must be performed'to maintain safe operating conditions, as determined by the Operations Super-visor On Shift
- b. ... may be performed without issuance, or approval, of a Maintenance Work Order (MHO), or procedure.
- c. ... must be approved by the General Manager or Deputy General Manager -AND- the OSOS or SS on duty.
- d. ... may be worked on a 24 hour / day, 7 day / week schedule, upon the specific approval of the General Manager.
QUESTION 8.09 (2.00) Answer the following TRUE or FALSE questions with regard to the control =of Lifted Wires and Temporary Jumpers (HNP-504 and HNP-9).
- c. A lifted wire or jumper that is required by Tech Specs, such as placing an inoperable channel in the tripped condition, does (0.5)
NOT require PRB approval.
"J b." When lifting wires or installing jumpers not requiring a and LW' sheet, 'd and LW' tags must still be placed on the (0.5) jumpers and/or lifted wires.
- c. The final approval to activate a 'J and LW' clearance sheet on
- c. safety system that is required to be operable by Tech Specs is provided by two members of the plant staff, one of whom must be a (0.5) licensed SRO.
- d. For surveillance procedures requiring the use of temporary jumpers, _ independent verification is ONLY required on system (0.5) restoration and NOT on initial installation.
~
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 30 4
OUESTION 8.10 (1.00) HNP-501, ' Equipment Clearance and Tassing', provides instructions for the proper method of requesting and issuing clearances and hold togs. Which of the following accurately describes the clearance process?
- o. When a maintenance project will require a clearance for more than ene shift, the Shift Supervisor can release the sub-clearance to the
- Maintenance Foreman't by name release is not required in this case.
- b. Any clearance which requires the normal electrical lineup of the plant to be modified, will be issued by the Shift Supervisor in the form of written Switching Orders, per HNP-X-1646.
- c. If a new MWO has identical isolation boundaries to a previously released MWO/ Clearance, the new MWO may be added to the clearance.
- d. When restoring a safety-related component to service, if NOT covered by procedure or surveillance requirement, INDEPENDENT VERIFICATION of the release is REGUIRED.
QUESTION 8.11 (1.00) Procedure MNT 01-0, ' Maintenance Program *, designates certain responsibilities for the Shift Supervisor in returning components / cystems to service after maintenance activities. Which of the following is NOT one of these responsibilities.?
- a. .The Shift Supervisor will EVALUATE the inspections and tests performed to determine if the systen. or component may be returned to service.
b.. The Shift Supervisor will PLACE the system or component in operation and DOCUMENT its operational status by signing the MWO.
- c. The Shift Supervisor will attach a copy of any LCO report gen-orated as'a result of the work activity to the NWO package, once the MWO is closed out.
- d. If the operational test (s) are UNSATISFACTORY, the Shift Super-visor will return the MHO, with amplifying remarks, to the Maintenance Foreman in charge of the work activity, to allow for further cor-rective maintenance to be performed.
.1
' ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 31 8.
GUESTION 8.12 (1.00) Unit 2 is in Operational Condition 1, at 75% RTP, with two outstanding
'daficiencies:
ADS 1 - ADS Valve INOP (1 Day) CS CST Suction INOP (3 Days)
.The Auto - swap of the HPCI suction upon receiving CST low level is determined to be UNSATISFACTORY. The suction is MANUALLY switched to the Suppression-Pool, and the suction to the CST is ISOLATED.
The Shift Supervisor determines that the required action (s), per the Unit Technical Specifications is(are) ...(CHOOSE ONE) NOTE: APPLICABLE TS's ARE ENCLOSED FOR REFERENCE
- o. ...no new limitations or TS-Operational Condition-restrictions are initiated by this re-alignment.
- b. ...be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam dome pressure to less than or equal to 150 psig within the fol-lowing _24-hours.
c .. ...be in at least HOT SHUTDOWN within 6 hours and COLD SHUTDOWN within the following 30 hours.
- d. ...be in at least HOT SHUTDOWN within-6 hours and reduce reactor eteam dome pressure to less than or equal to 150 psig within the ne::t 30 hours.
9 0 4 4
-,.--,a.~ . , - - , , , - , - - ,- , . -- ~ s, , e - - , . . . - - - , . _ - - ,, - .-+--,r-,,- , - . , -
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 32 A
QUESTION 8.13 (1.00) Procedure HNP-514, ' Control of Locked Valves'e states that ...
"... Confirmation of valve position is required periodically ... (and) all valves will normally be checked and manipulated by Operations Depart-ment personnel ...'
What is the proper _way to CONFIRM a locked valve position?
- o. Turn the valve hand wheel in the OPEN directioni confirm the locking device integrity and proper installation by visual inspection.
- b. Turn the valve hand wheel in the CLOSED directioni confirm the locking device integrity and proper installation by attempting to misposition the valve.
- c. Turn the valve hand wheel in the DESIRED POSITION directioni confirm the locking device integrity and proper installation by visual. inspection.
- d. Turn the valve hand wheel in the DESIRED POSITION directioni confirm the-locking device integrity and propee installation by ettempting to misposition the valve.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 33 8.
.g 8.14 ' (1 00)
QUESTION Unit 2 is in C08.D SHUTDOWN during a reactor strartup with no outstanding deficiencies. Hydrogen Recombiner A becomes INOP. It is anticipated that repairs will be complete within two (2) ' weeks. The Shift Supervisor determines that the required action (s) per the Unit 2 Technical Specifications is(are) ... (CHOOSE ONE)
- e. ... Operational Condition 4 must be maintained (Entry into Operational Condition 5 is acceptable)
- b. ...Startup activities may continue; Operational Condition 3 may be entered, but not exceeded.
- c. ...Startup activities may continue; Operational Condition 2 may be entered, but not exceeded; OxySen concentration shall be maintained < 2 v/o.
- d. ....Startup activities may continue; Operational Condition 1 and/or 2 may be entered, but the Recombiner must be returned to en OPERABLE status within 30 days.
NOTE: APPLICABLE TS's ARE ENCLOSED FOR REFERENCE
.T 2
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 34 j
~
GUESTION 8.15 (2.00)
- o. Unit 2 is in Operational 1 Condition with NO outstanding deficien-cies. .The current Surveillance Assignment printout sheet' identifies a
" Latest Date' for the RCIC quarterly flow teste but the RCIC system I becomes INOPERABLE before completing the surveillance. SELECT the statement which accurately. describes the surveillance requirements'as per.HNP-831, ' Tech Spec Surveillance Program.' (1 0) ,
(1) The surveillance must be performed immediately AFTER returning the system-(or subsystem) to an OPERABLE condition.
-(2) The next regular surveillance interval.shall commence UPON THE COMPLETION of the overdue surveillance.
.(3) The surveillance shall NOT be_ documented as officially .
missed until the END of the " Latest Date.' l
-(4) Since the RCIC system is already INOPERABLE, an LCO sheet i l
need NOT be issued to track the missed surveillance. b.. The
- Earliest Date' block of the Surveillance Assignment printout cheet reads '00000* for a given surveillance. STATE the meaning of this-reading AND for which Unit it would be applicable. (1.0) ,
1
g c
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 35
, mn
-itCC W;
QUESTION 8.16: EP (1.00) Unit 2 has been recently shutdown and placed in COLD SHUTDOWN - Operational Condition 4. The shutdown /cooldown was necessitated by a requirement to drain and visually inspect the Suppression Pool. The following plant conditions / requirements have been established: CS system is ali3ned to the CST Reactor Mode Switch is locked in the Shutdown Position No maintenance affecting the reactor vessel is in progress i There is one outstanding deficiency: D/G 2A Turbocharger is undergoing repairs (D/G INOP) NOTE' APPLICABLE TS's ARE ENCLOSED FOR REFERENCE The Shift Supervisor may ...(CHOOSE ONE)
- a. ... commence Suppression Pool draining, since all TS LCO require-cents are met.
- b. .... commence Suppression Pool draining as soon as he ensures that.NO POSITIVE REACTIVITY changes will occur during this condition.
- c. ... commence Suppression Pool draining as soon as he ensures that NO POSITIVE REACTIVITY changes will occur AND that one LPCI cubsystem is OPERABLE in this condition.
- d. -... commence Suppression Pool draining only AFTER the D/G 2A Turbocharger is repaired and the D/G declared OPERABLE.
i
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, MA5 i k:. E
. C O?Y g
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 36 y
ANSWERS -- HATCH 112 -85/03/11-K E BROCKMAN ANSWER 5.01 (1.00) d REFERENCE EIH, L-RG-605 (15) ANSWER 5.02 (1.00) 0 REFERENCE EIH, L-RG-602 ANSWER 5.03 (1.00) d REFERENCE General Electric, NEDE-24810 (Jun 81) ANSWER 5.04 (1.00) o REFERENCE Steam Tables ANSWER 5.05 (2.00)
- e. (2) - Starting Pump 2 (0.5)
- b. Curve B (0.5)
(0,5)
- c. INCREASE
- d. Curve C (0.5) i REFERENCE Pump Laws -
l
i ..
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 37 ygg g--------------------------------------
ANSWERS'-- HATCH 182 -85/03/11-K E BROCKMAN ANSWER 5.06 (1.50) F1. b F2. c F3. a L1. c L2. a L3. b (.25 each) REFERENCE EIH, GPNT, Vol VII, Chapter 10.2-23 ANSWER 5.07 (1.00) d REFERENCE EIH, L-RG-667 (3), L-RO-654 ANSWER 5 08 (1 00) b- OP - d REFERENCE EIH, GPNT,Vol VII, Chapter 10.1-83-06 ANSWER 5.09 (1.00) 0 REFERENCE EIH, L-RG-675 ANSWER 5.10 (2 50')
- s. Recirculation Pump Trip (Lo Lo Level)
- b. MSIV Closure (Lo Lo Lo Level) - OP - CV Closure w/BPV r.S.
- c. HPCI E RCIC Injection
- d. HPCI erid PCIC Cooldovr. Effeett (Steen f Colder Vater)
- e. Recirculation Punip Runback (41 S.L.) (0.5 each)
b THEORY OF NJCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 38 5. y ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN REFERENCE EIH, L-RQ-732 ANSWER .5.11 (2 50)
- c. Natural Circulation at reduced power (Scram)
- b. Decreased suction from the downcomer due to the tripped RRP's (Increased voiding in the core causing a swell in the downcomer)
- c. In response to level increase
- d. Loss of FW Heating (due to reduced extraction steam flow)
- o. EHC established flow appropriate to control pressure (Flow equivalent to reactor power) (0.5 each)
REFERENCE EIH, L-RO-732 ANSWER 5.12 (1.00) b REFERENCE EIH, L-RQ-667 (10) l ANSWER 5.13 (J'.00)
- . '2 De.\ded
- b. (1)
REFERENCE EIH, L-RG-672 (15); U2 TS 3.2.3 ANSWER 5.14 (1.00) d REFERENCE EIH, L-RG-602 (9) _ , - , ~ , , - . , -. ._ _ - _en.
4 . THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 39 5.
---- y--------------------------------------
ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN ANSWER 5 15 ( .50) FALSE ~ REFERENCE EIH, L-RG-603 (4) l l
. l
E PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 40 6.. ANSWERS -- HATCMJ182 -85/03/11-K E BROCKMAN ANSWER 6.01 (1 00)
-b REFERENCE EIH, L-RQ-752, DCR 80-111; L-RG-734 ANSWER 6 02 (1.00) a.
REFERENCE EIH, L-RG-752; DCR 81-175; GPNT, Vol V, Chapter 4.5; GPNT, Vol VII, Chapter 8.1 ANSWER 6.03 (1.00) c REFERENCE EIH, GPNT, Vol VI, Chapter 7.2; EIH Simulator ANSWER 6.04 (1.00) c REFERENCE EIH, GPNT, Vol V, Chapter 4.1-9; GPNT, Vol VI, Chapter 5.'5-10; GPNT, Vol VII, Chapters 9.2.2-11 and 9.2.3-5 ANSWER 6.05 (1.00) c REFERENCE EIH, GPNT, Vol V, Chapter 4.1-23 ANSWER 6.06 (1.00) d
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 41 6.. CNSWERS -- NATCH 142 -85/03/11-K E BROCKMAN 4 REFERENCE EIH, GPNT, Vol V, Chapter 4.3-12 ANSWER 6 07 (1.00) O REFERENCE EIH, GPNT, Vol V, Chapter 5.1.II.B ANSWER 6.08 (2.00)
- 5. To prevent a loss of reactor water inventory to the Torus (0.8) through the Minimum Flow Valve (0 2) -
SDC PCIS Valves (F008 & F009) Auto Close b. All runnins RHR Pumps - Trip Head Spray Valve (F023) - Auto Closes RHR Inboard Inj. Valve (F015) - Auto Closes (2 reg'd 0 0.5 each) REFERENCE EIH, GPNT, Vol V, Chapter 4.4-15,17; GPNT, Vol VI, Chapter 8.3.c.3; HNP-2-1114, p6 ANSWER 6.09 (2.00)
- e. 1.85 psis (.25) in Drywell (.25) and/or to Lo Level (.25) of - 55 inches (.25)
- b. (1) WILL (2) WILL (3) WILL NOT (4) WILL (.25 each)
REFERENCE EIH, GPNT, VOL VI, Chapter 8.1 ANSWER 6.10 (1.00) . b REFERENCE EIH, L-RG-733, pit, Fig 4
3 6 60 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 42 ANSWERS -- HATCH 112 -85/03/11-K E BROCKMAN ANSWER 6.11 (1.00) c REFERENCE EIH, L-RG-752; DCR 79-442; HNP-1-1500 ANSWER 6.12 (1.00) b REFERENCE EIH, GPNT, Vol VI, Chapter 5.37 DCR 83-87 ANSWER 6.13 (1.00) b- OP - d REFERENCE EIH, GPNT, Vol. V, Chapter 4.1-26; L-RO-714 (14) ANSWER 6.14 (1 00) d REFERENCE EIH, L-RG-719 (6,9); L-RO-720 (10) ANSWER 6 15 (1.00) b REFERENCE EIH, L-RO-704 (6) s 1
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 43 6. ANSWERS -- HATCH 112 -85/03/11-K E BROCKMAN ANSWER 6 16 (2.00) PARAMETERS MONITORED Vessel level is monitored and becomes the controlling signal (0.5) for operation of the Startup Level Control (F111) valve. dP signal across the SLC Bypass Valve (F110) is monitored and (0 5) becomes the controlling signal for RFPT speed. SYSTEM / COMPONENT CONTROL The input to the M/A stations is a dP error signal from the dP controller. The controller senses the dP across the F110 valve, compares it to the controller set dP, in order to maintain a (0 5) constant dP across the valve. The F111 valve opens / shuts in response to reactor vessel water level. When the valve opens, the dP decreases and the signal sent is to increase RFPT speed; valve closure is the converse. (0.5) REFERENCE EIH, L-RO-726 (3,5,6) ANSWER 6.17 (1.00) INCREASE (0.5) The vacuum breaker provides a direct path to the DRYWELL. (0.5) REFERENCE EIH, GPNT, Vol V,' Chapter 3.1; NUREG/BR-005/Vol 5, No 4, Power ~ Reactor Events, Jan 84, p5 (Hatch occurance 8/25/82)
s
- 7. ' PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 44
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~Rd65UL55fCaE cUNTEUL ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN ANSWER 7.01 (2.00) a).1. RPV level cannot be maintained (0 5)
- 2. Suppression Pool water temperature cannot be maintained below 110 des F (0.5) b) 1. Five (5), or more adjacent control rods not insertec below the 06 position (0.5)
- 2. Thirty (30), or more total control rods not inserted below the 06 position. (0.5)
REFERENCE EIH, HNP-2-1909 i I ANSWER 7.02 (1.50) a) ROUTINE (0.5) b) REGULAR (0.5) c) BLANKET (0.5) REFERENCE EIH, HNP-8008, pp 1, 6, 8 ANSWER 7.03 (1.00) c REFERENCE EIH, HNP-2-1903, p2 ANSWER 7.04 (1.00) d REFERENCE EIH, HNP-2-1910 ANSWER 7.05 ( .50) Every five (5) minutes (1/2 credit for more conservative response)
l l
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 45
~
~~~~R 5656[6656AL UNYE E"~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- HATCH 182 -85/03/11-K E BROCKMAN REFERENCE EIH, GET Handbook, p25 ANSWER 7.06 (1.00) b REFERENCE EIH, HNP-2-1946 ANSWER 7.07 (1.00) j b REFERENCE EIH, HNP-2-1902 ; ANSWER 7.08 (1.00) j l a REFERENCE EIH, HNP-2-1015 ANSWER 7.09 (1.00) a) + 570
- from Vessel Zero -OR- + 53' from Instrument Zero (0.5) b) (a flow path for) Natural Circulation (0.5)
REFERENCE EIH, HNP-2-1932 ANSWER 7.10 (1.00) d REFERENCE EIH, HNP-2-1928 1
- 7. -PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 46
~~~~~~~~~~~~~~~~~~~~~~~~
l
~~~~~EI656E665CIE~EUITR6L
-85/03/11-K E BROCHMAN j ANSWERS -- HATCM 182 ANSWER 7.11 (1.00) ,
I e REFERENCE I ' EIH, HNP-2-1934,p1 ANSWER 7.12 (2.00) d (.25); fr.c, b (.75); 9 (.25); h (.25); e (.25); a (.25) REFERENCE l l EIH, HNP-2-1001, pp 18, 19, 20, 22, 23, 28, 29 l ANSWER 7.13 (1.00) l o-REFERENCE EIH, HNP-2-4207, p2 ANSWER 7.14 (2.00)
'B' is normally selected because a failure in the 'A/C'
-side, causing the-transniitters to sense a L0u level, would y cause the following:
-A turbine trip on High Level (58') would-not occur (0.5)
If 'A' transmitter were selected, a false signal would be sont out to the controllers to increase level (0.5)
- Lovel would continue to increase until the operator i torminated the transient I
With "B' selected, a failure of the 'A' transmitter would l-not result in level change since the 'B' transmitter has not failed. (But still do not have 2 out of 3 trip available) (0.5) Failure of 'B' transmitter with 'B' selected would cause water level change, but the 2 out of 3 trip would still provide (0.E) protection. 1 E _ . _ _ f
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 47
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~~~~RI656L66f65E~66UTE6L ANSWERS -- HATCH 142 -85/03/11-K E BROCKMAN REFERENCE {
EIH, L-RG-726; GPNT, Vol VI, Chapter 5.3 l f [ ANSWER 7.15 (1 00) To preclude establishing excessive stresses in the jet pumps due to flow reversals - OR - to prevent excessive radial bearin3 loads (on the recite pumps) REFERENCE
-EIH, HNP-2-1437, p5; GPNT, Vol V, Chapter 4.1 ANSWER 7.16 (1 00)
Ma::imum licensed thermal power'may be exceeded in the
- instances of THERMAL SPIKES.(0.5) Verification is
! cecomplished by use of OD-3 Printouts from the Process t Computer.(0.5) l RE.FERENCE l EIH, HNP-2-1005, pp 1,2 l t ANSWER 7.17 (1.00) a REFERENCE EIH, HNP-2-1930
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 48 8. ANSWERS -- HATCH 142 -85/03/11-K E BROCKMAN ANSWER 8 01 (1.00) a REFERENCE EIH, U1TS, 1.1.c ANSWER 8.02 (1.00) e REFERENCE EIH, U2 TS, 3.0.4, 3.3.1, 3.3.2 ANSWER 8.03 ( .50) SHIFT SUPERVISOR (SS) or OPERATIONS SUPERVISOR (OSOS) or ANY HIGHER RANKING LICENSED OR CERTIFIED PERSON PRESENT REFERENCE EIH, HNP - 4520, 4620, 4720 ANSWER 8.04 (1.00) a) 12 hours (+ 0) b) 92 days (+ 0) c) 31 days (+ 0) (.25 esch) d) R REFERENCE EIH, U2 TS, Table 1.1; HNP-0-ADM-0831 ANSWER 8.05 (1.50) (1) Highest worth rod (0.25) fully withdrawn (0.25) (2) Xenon free (0.5 each) (3) Cold (68 des F) REFERENCE EIH, U2 TS, 1.0 'SDM'
)
6 w , 8.' ADMINISTRATIVE PROCEDURES, . CONDITIONS, AND LIMITATIONS PAGE. 49 ANSWERS -- HATCH'182 -85/03/11-K E BROCKMAN ANSWER ~ 8.06 (3.00) a) UNIDENTIFIED LEAKAGE increased from a 2.51 gpm rate at 0400.to a 4.58 gpm rate at 2000, thus exceeding the 2 spm increase limit within a 24 hour (0.67) Periode TOTAL LEAKAGE exceeded the 25 spm limit over a 24 hour period (25.50 SPm) (0.66) UNIDENTIFIED LEAKAGE exceeded the 5 gpm limit (0.67) at 2400 (5.2 SPm) Hb ) Pressure Boundary Leakage is leakage through a non-isolable fault (0.5) in a reactor coolant system component' body, pipe wall, - or vessel wall (0.5) (1.0) REFERENCE EIH, U2 TS, 10, 3.4.3.2; Confirmatory Order 7590-01, dtd 7-8 ANSWER 8.07 (1.00) e - OR - c REFERENCE
.EIH, HNP - 9, p47 ANSWEF S.08 (1.00) b REFERENCE EIH, MNT 01-0, p9 ANSWER 8.09 (2.00) a) TRUE' b) TRUE c) FALSE d) TRUE REFERENCE EIH, HNP-504, pp 1-3; HNP-9, p25
s' - I i %) ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 50 8. __________________________________________________________ l ANSWERS -- HATCN1.182 -85/03/11-K E BROCKMAN ;
-ANSWER 8.10 -(1.00) c REFERENCE
'EIH, HNP-501, pp 1, 2, 8, 10 ANSWER 8 11 (1.00) d REFERENCE EIH, MNT 01-0, p20 ANSWER 8.12 (1.00) c REFERENCE EIH, U2 TS, 3.5.1, and 3.5.2 ANSWER 8.13 (1 00) b REFERENCE EIH, HNP-514, p1 ANSWER 8.14 (1.00) d REFERENCE EIH, U2 TS, 3.0.3, 3.0.4, 3.6.6.2
- i. ,
G
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 51 CNSWERS -- HATCHf182 -85/03/11-K E BROCKMAN ANSWER 8.15 (2.00)
(1.0)
- o. (3) b.- '00000' indicates that there is no Negative Grace Period for this surveillance.(0.5) It would be applicable for Unit 2. (0.5)
(Since Unit 1 allows plus AND minus 25% interval variance) REFERENCE EIH, HNP-ADM-0931 ANSWER 8.16 (1.00) d REFERENCE EIH, U2 TS's, 3 5.4; Standing Order 84-35 1
- - - , , - ,. , . . , . - , ,, , , . , , - n .,_---,,-_$... .l .n-- - ,-- - . . . . - - , - - , - , , ,
9. o
-TEST CROSS REFERENCE PAGE 1
. QUESTION VALUE REFERENCE 05.01 1.00 KEB0000042 05.02 1.00 MEB0000043 05 03 1.00 KEB0000044 05.04 1.00 KEB0000045 03.05 2.00 KEB0000046 05.06 1.50 KE60000047 05.07 1.00 KEB0000048 05.08 1.00 KEB0000049 KEB0000050 05 09 1.00
.05 10 2.50 KEB0000051
'05 11 2.50 KEB0000052 05.12 1.00 KEB0000053 05 13 2.00 KEB0000054 05 14 1.00 KEB0000055 05.15 .50 KEB0000056 20.00 06.01 1.00 KEB0000030
-06.02 1.00 KEB0000031 06.03 1.00 KEB0000032 06.04 1.00 KEB0000033 06.05 1.00 KEB0000034 06.06 1.00 KEB0000035 06.07 1 00 KEB0000036 06.08 2 00 KEB0000037 04.09 2.00 KEB0000038 06.10 1.00 KEB0000039 06.11- 1.00 KEB0000040 06.12 1.00 KEB0000041 u06.13 1.00 KEB0000060 06.14 1.00 KEB0000061 06.15 1.00 KEB0000062 06.16 '
2 00 KEB0000063 06.17 1.00 KEB0000064 20.00 07.01 2.00 KEB0000016 07.02 1.50 KEB0000017 07.03 1.00 KEB0000018 07.04 1.00 KEB0000019 07.05 .50 KEB0000020 07.06 1.00 KEB0000021 07.07 1.00- KEB0000022 07.08 1.00 KEB0000023 07 09 1.00 KEB0000024 07 10 1.00 KEB0000025 07.11 1.00 KEB0000027 07.12 2.00 KEB0000028 L
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c a-TEST CROSS REFERENCE PAGE 2 00ESTION VALUE REFERENCE 07.13 1.00 KEB0000029 07.14 2.00 KEB0000057 07.15 1.00 KEB0000058 07.16 1.00 MEB0000059 07.17 1 00 KEB0000136 20.00 08.01 1.00 KEB0000001 08.02 1 00 KEB0000002 08.03 .50 KEB0000003 08.04 1 00 KEB0000004 08 05 1.50 KEB0000005 08.06 3.00 KEB0000000 08 07 1.00 KEB0000009 08.00 1.00 KEB0000010 08 09 2.00 KEB0000011 08.10 1.00 KEB0000012 08.11 1.00 KEB0000013 08.12 1.00 KEB0000014 08.13 1.00 KEB0000015 08.14 1.00 KEB0000092 08.15 2.00 KEB0000134 08.16 1 00 KEB0000135 20.00 80.00
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No. N-N a Date-Issued //ON ' Date Deleted' TITLE CLARIFICATION OF OPERABILITY APPROVED , e y #/r/G'A _ % nager och of Operations, &fm+-- or
, Site General / Manager or Site Deputy General Manager Superintendent of Operations The following clarification of the definition of operability is now in effect. Any questions concerning interpretation of the below beyond what is explicitly stated in the statement below should be referred to the General Manager or Deputy General Manager.
.; When a system, subsystem, train component, or device having Technical Specification operability requirements is determined to be inoperable:
I solely because'its emergency power source is inoperable, or solely, because its normal power source is inoperable, it may be considered L .- operable for the purpose of satisfying'the requirements of its - applicable Limiting Condition for Operation, provide d: (a)'its ' corresponding normal or emergency power source is operable; and (b) all its redundant system (s), subsystem (s), train (s) component (s) and t
' device (s) are operable, or likewise satisfy)the requirements of titis specification. Unless both condition (s) (a and (b) are satisfiedi enter the applicable Limiting Condition for Operation as specified by the Technical Specifications, or the unit shall be placed in at , <
least Hot Shutdown within the next 6 hours, and in at least Cold t Shutdown within the following 30 hours. The clarification stated abov'e is not applicable in Operational
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3.3.17 As a minimum, the reactor protection system instrumentation chan shown in Table 3.3.1-1 shall be OPERA!LE L with theare Set poihts and interlocks. REACT RESPONSE TIME as shown in Table 3.3.1-2. given in Table 2.2.1-1. . '
- .' APPL:CASILITY: As shown in Table 3.3.1-1.
w ACTIOM: a. h'ith the requirements for the mir.imum number of OPERAELE channels not satisfied for one trip system, place at least one inoperable channel in the tripped condition within one hour, b. l'ith the requirements for the minimum n' umber of OPERABLE channels not satisfied for both trip systems, place at least one inoperable channel in at least one trip system
- in the tripped condition within one hour and take the ACTIOi; required by Table 3.3.1-1.
- c. The provisions of Specification 3.0.3 are not applicable in OPERA-TiONAL C0:J31T10N 5.
- SURVIILLANCE RE0tt!RIMir:TS .
+11 so;n cnanneis are inoperable in ene trip sy Tric Function te occur.
cact-: when tnis cc'.1d cause the A .cnd cr.t lM. E 3/4 3-1 HAIC;- - Uf!!T 2 t
r TABI.E 3.3.1-1, , REACTOR PROTEC1 ION SYSTEH INSTRiflENTATION , APPLICABI.E HINItft#f NIRfBER - OPERATIONAL OPERABI.E CllANNELS. g N FilNCTIONAI. IINIT - CONDITIONS PER TRIP SYSTEH(a) ACTION 9 '
- l. Intermediate Range Honitors:
h e (2C51-K601, A, B, C, D, E, F, G, N) ~
- a. Neutron Flux - liigli 2(c) 5 3 1 -
- b. Inoperative 3,
2,5 g) 2 2 3 1 3,4 2 2
- 2. Average Power Range Honitor:
(2C51-K605 A, B, C, D, E, F) .
- a. Neutron Flux - Upscale, 15% 2, 5 3
2
- I le . Flow Referenced Simulated
- h Thermal Power - tipscale 1 2 3
- c. Fixed Neutron Flux -
Y tipscale, 118% 2
" 1 3
- d. Inoperative 1, 2, 5 2 4
- e. Downscale 1 2 3
- f. I.PRil 1, 2, 5 -
(d) NA
- 3. Reactor Vessel Steam Dome Pressure -
liigli (2B21-N678 A, B, C, D) 1, 2(e) 2(J, 2B21-N045 5 A, B, C, D) l g
- 4. Reactor Vessel Water Lev'l e -
- g. I.nw (Level 3) (2B21-N680 A, B, C, D) I, 2 2(j, 2821-N681 A, B, C, D)
S ' g 5. liain Steam Line Isotation Valve - Closure (NA) 1(g) 4 3 w 6 Hain Steam Line Radiation - Nigli 1, 2(c) - 6 U (2DII-K603 A, B, C, D)
- 7. Drywell Pressure - liiglo I, 2 f8) 2 5 (2C71-N650 A, B, C, D) .
s. Tant.R 3.1.1-1 It end linied) MiAC10R Plant 14rTION SYDtiM ,Ileft1aDGMFATION e A4't't.Irmit1: NIN194M DEMWtR g (Mt34ATit NAI. (Mt34AIEE OtADee:IS 70 H g FISCTf0090 tmlT (t MitTil eti PtM 'litIP SY9ttM(a) ACTWM -
- 8. Scrain Discharge volume mter '
; .i la Invel - Illgh (2Cll-Isi!3A,II,C,f)) 1, 2, SII'I 2 4
- tevel - Istgh (2C11-N060A It,C,II) I, 2, 5 2 4l
- 9. Turtilne Stop Valve - Cloeure (NR) 1(I) 4 (k) .7
- 10. 'nathine Gintrol valve Fast Cleweisre, Trip 011 Pressure - Isme l(ll 2(k) 7 (2c71-N005A,B,C,D) *
- 11. Reactor pede sheitd in filmitstown Position (NR) 1,2,3,4,S 1 8
- 12. Manual Scrass (NA) I,2,3,4,5 1 9 3
9 . 2<> - - q
c . TABLE 3.3.1-1 (Continued) REACTOR PROTECTION SYSTEM INSTRUNENTATION '
.4 ele. . .
ACTION 1 - In OPERATIONAL CONDITION 2. be in at least HDT SHUTDOWN within 6 hours. l In DPERATIONAL CONDITION 5. suspend all operations involving CORE ALTERATIONS or postive reactivity changes and fully insert all insertable control rods within one hour. ACTION 2 - Lock the reactor mode switch in the Shutdown position within one hour. - ACTION 3 - Se in at least STARTUP within 2 hours. , l
~
In OPERATIONAL CONDITION 1 or 2. be in at least NOT SHUTDOWN ACTI'ON 4 - within 6 hours. l. In OPERATIONAL CONDITION 5. sussend all operations involving CORI ALTERATICNS or positive reactivity changes and fully insert all insertable control roos within one hour. 1 ACTION 5 - Be in at least NOT SHUTDOWN,within 6 hours. ACTION 6 - 'Be in STARTUP with the main steam line isolation va'1ves closed within 2 hours or in at least HOT SHUTDOWN within 6 hours. ( ACTION 7 - Initiate a reduction in TH5RMAL POWER within 15 minutes and be at less than 30t of RATED THERMAL POWER within 2 hours. ACTION 8 - In OPERATIONAL CONDITION 1 or 2. be in at least HOT SHUTDOWN within 6 hours. l In OPERAT:0NAL CONDITION 3 or 4. istnediately and at least once per 12 hours verify that all control rods are fully inserted. In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour. HATCH - UNIT 2 3/4 3-4 Amendment No. 8
1 l
' TABLE 3.31-1 (Continued) -
\
l ' EACTOR PROTECTION SYSTEM INSTRUDENTATION I ACTION 9:- In OPERATIONAL CDCITION 1 or 2, be in at least PCT SHUT 00WN ; within 6 hours. l In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch l in the Shutdown position within one hour. In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour. TABLE NOTATIONS
- a. A channel ma/ De pinced in an inoperable status for up to 2 hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system '
is monitoring that parameter.
- b. The " snorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accor ance with Specification 3.10.3.
- c. The IRM scrans are automatically bypassed when the reactor vessel mode i switch is in the Run position and all APRM channels are OPERASLE and on scale.
- d. An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.
- e. These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.
f. This function is automatically bypassed when the reactor mooe switch is in other than the Run position. CONTA:tNEt.T
- g. This fun: tion is not recuired to be OPESABLE when PRIMA 9Y INTEGGITY is not reoJirec; this function may be bypassed when necessa:y for contain .ent inerting or c'e-inerting (purging).
- h. With ay control rod withdrawn. Not applicable to control ' rods remeved per Specification 3.9.11.1 or 3.9.11.2. '
- 1. These functions are bypassed when turoine first stage pressure is 1250+
psig, equivalent to THERKAL P0nIR less ther ;fa of RATED THERMAL P J. Also trips reactor coc1&nt system recirculation pump HG sets.
- k. Also trips reactor coolant system recirculation pump motors.
t
- initial set;.cint.
Final setpoint to be determined durirg startup testing. Amendment No. $. 29 1 FATCH - UNIT 2 3/4 3-5 . I e
"N l
.- INSTRUP.ENTATION
.f 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION
. s LIMITING CONDITION FOR OPERATION .
3.3.2 :The isolation actuation instrumentation channels shown in Table 3.3.2-1:shall be OPERABLE with their trip setpoints set consistent with the
. values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.
APPLICABILITY: As shown in Table 3.3.2-1. ACTION:
- a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition
- until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place at least one inoperable a channel in the tripped condition
- within one hour.
o
. c. With the requiremen'ts for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoper-able channel in at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table -
3.3.2-1.
- d. The provisions of Specification 3.0.3 are not applicable in
. ' OPERAT10flAL C0fiDITION 5.
SURVEILLAtlCE REOUIREMENTS 1 I
- Witn a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTICN required by Tele 3.3.2-1 for that Trip Function shall be taken.
'If bc!h channels are incperable in one trip syster., select at least one inoperable channel in that trip system to place in the tripped conditien, except when that would cause the Trip Function to occur. '
HATCH - UNIT 2 3/4 3-9 Amendment No. 8
' r z ,
39 y ,. , ...
~ '
TARII. . 2-1
. . I .
ISOI.ATION ACTUATION INSTRIRfENTATION
< {
p , VALVE GROUPS HIN1Hitt NUMBER APPLICABLE
*a OPERATED BY OPERARI.E CilANNELS OPERATIONAL $$ z THIP flINCTim j ,, SIGNAI.(a) PER TRIP SYSTEN(b)(c) CONDIT10Il ACTION
- 1. PRIHARY C NTAINtfENT ISOLATION '
- a. Heactor Vessel Water Level '
- 1. Low (Level 3) , ' #-
f , 2, 6, 10, 2' ,. 1, 2, 3 20 (2821-N680 A, B, C, D) II, 12'
- 2. Low-I.ow (i.evel 2) 5, #, * ' 2 1, 2, 3 20 (2821-N682 A, B, C, D)
- 3. Low-Low-1.ow (Level 1) I 2 .
I, 2, 3 20 (2021-N681 A, B, C, D) - Is . Drywel1 Pressure - Nigh 2, 6, 7, 10, 2 I, 2, 3 , 20 (2C71-N650 A, B, C, D) l 12, f,
- 4 .
u c. Main Steam Line D 1. Radiation - High 1, 12, f, (d) 2 I, 2, 3 21 u (2DIl-K603 A, B, C, D) 1
~
2.* Pressure - Low 1 2 1 22 (2B21-N015 A, B, C, D)
- 3. Flow - liigh 1, # 2/line 1, 2, 3 21 (2821-N686 A, B, C, D) -
(2H21-N687 A, B, C, D) (2B21-N688 A, R, C, D) (2821-N689 A, B, C, D) , l
- d. Main Steam Line Tunnel .-
h Temperature - liigh 1 2/lineI
- 1, 2, 3 21
= (2R21-N623 A, B, C, D)
- g. (2B21-N624 A, B, C, D) ,
g (2821-N625 A, B C, D)
<* (2B21-N626 A, B, C, D)
- e. Condenser Vacuum - Low 1 2 I, 2, ,3 23 (2821-N056 A, B, C, D) g f. Turliine Building Area g)
Temperature.- Nigh 1 2 1, 2, 3 21 (2tl61-R001, 2U61-R002, 2U61-R003, , 2tl61-R004) . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ __
TARI.E 3.3.2-1 (Cont i sjued) ISOT.ATION ACTilATION INSTRIltlENTATION , f VAT.VE GROUPS HINIHUN NUMBER APPI.ICABI.E d - OPERATED llY OPERABI.E CilANNELS OPERATIO11AL 7 Tit lP FilHCTION
-" SIGNAI.(a) PER TRIP SY3TEH(b)(c) CONelTIN ACTI0ff Q
N 2. SECONI)ARY CONTAINHENT ISOf.ATION .
- a. Reactor fluilding Exhaust.
Railiation - liigli 6, 10,- 12,
- 2 1,2,3,5 and** 24 (2illl-K609 A', B, C, D)
- h. DrywcIl Pressure - liigh 2, 6, 7, 10, 2 1,2,3 24 (2C11-N650 A, B, C,!)) 12, f, *
- c. Reactor Vessel Water I.cve t - I.ow I.ow (i.evel 2) 5, f ,
- 2' 1, 2, 3 24
, (2il21-N682 A, B, C, D) . 's? el . Refueling Floor Exhaust Railiation - Iligh , 6, 10, 12, f,
- 2 1,2,},5 and** 24 so (2Dil-K611 A, B, C, D) ,
- 3. MACTOR WATER Cf.EANUP SYSTEH ISOI.ATION
~
- a. A Flow - liigh (2G31-N603 A, B) 5 1 1, 2, 3 25
- h. Area Temperature - liigh 5 1 1,2,3 25 (2G31-N662 A, D, E, II, J, it) l .
> c. Area Ventilation a Temp. - Iligh 5 I 1, 2, 3 25 @ (2G31-N663 A, D, E,11, J, it; , & 2G31-N661 A, D, E, II, J, ti; @ 2G31-N662 A, D, E,11, J,11) 5 2 d. SI.CS Initiation (NA) S IEI NA 1, 2, 3 25 P . w
- c. Reactor Vessel Water T.evel - I.ow I.nw 5. f,
- 2, 1, 2, 3 25 (l.cvel 2) (2821-N682 A, B, C,I)) , , ,
TARI.E 3.3.2 (Continued) ' ISOLATION ACTilATION INSTRIMENTATION
- r n
9 ~ VALVE GRollPS HININiff NIMBER APPLICABLE h 4 OPERATED IlY OPERARI.E CllANNELS OPERATICIIAL g T._R_IP FilHCTION SIGNAI.(a) PER TRIP SYSTEN(b)(c) CollDITIM ACTICIt
- 4. IIIGil PRESSilRE COOLANT INJECTION SYSTEN ISOLATION .
- a. IIPCI Steam Line Flow - High 3 1 1, 2, 3 26 (2E41-N657 A,B).
l
- h. IIPCI Steam Supply Pr' essure -
- I.ow (2E41-H658 A,B,C,D) 3,8 2 1, 2, 3 26 l
- c. IlPCI Turbine Exhaust Diaphragm Pressure - liigh (2E41-N655 A,R,C,D) 3 2, 1, 2, 3 26 l u
U d. IIPCI Pipe Penetration Room . w Temperature - liigh (2E41-N671 A, B) 3 - 1 1, 2, 3 26 l
- e. Suppression Pool Area Ambient Temperature-liigh (2E51-N666 C, D) 3 1 , 1, 2, 3 26
- f. Suppression Pool Area
- o Temp.-liigh (2E51-N665 C, D; -
3 1 1, 2, 3 26 3E51-N663 C, D; 2E51-N664 C, D)
- y g. Suppression Pool Area Temperature 3 Timer Relays (2E41-N603 A,11) 3 g
" 1 1, 2, 3 26 s @ h. Emergency Area Cooler Temperature-liigh (2E41-N670 A, B) 3 1 1, 2, 3 26 l I
- i. Drywell Pressure-fligh * *
(2 Ell-N694 C, D) .] - 8 I 1,' 2, 3 26 J. Logic Power Honitor (2E41-KI) , NA(h) I 1, 2, 3 27
.. g
~
TARI.E 3.3.2-1 t:entinued) t ISol.ATION ACTUATION INSTRtRif.NTATI0li - VAI.VF. CROllPS HINIHilH NilHRER APPI.ICARIE. OPERATED BY OPERARI.E CllANNELS OPERATIONAL p THIP FilNCTION
*8 5. REACTOR CORE IS01.ATION SIGNAI.(al PER TRIP SYSTEN(b)(c) 'CONDITICII _
ACTIGH h C001.ING SYSTEH ISOI.ATION - r),
- a. , s ~~
- 7) RCIC Steam Line Flow-liigh 4 I 26 g
1, 2 -3 ' I m (2E51-N657 A R) , l l
- h. RCIC Steam Supply Pressure -
I.ow (2E51-N658 A, R, C, D) 4, 9 2 1, 2, 3 26 l_
- c. RCIC Turbine Exhaust '
Diaphragm Pressure - High 4' 2 1, 2, 3 26 (2E51-N685 A, R, C, D) . l. w d. Emergency Area Cooler Temperature - .. liigh (2E51-N661 A, 8) 4 1 1, 2, 3 26 8-
- e. Suppression Pool Area Ambient Temperature-High 4 1 1, 2, 3 26
'(2E51-N666 A, R)
- f. Suppression Pool Area A T-High 4 1 1, 2, 3 26 (2E51-N665 A, R; 2E51-N663 A.R; i 2E51-N664 A,R)
- g. Suppression Pool Area Temperature Timer Relays (2E51-H602 A, B) g 4, 1 1,2,3 26
- h. Drywell Pressure - High y (2E11-N694 A, R) 9 1 1, 2, 3 26 E '
l, y i. I.ogic Power Monitor (2E51-KI) NA(h) 1 1, 2, 3 27 S 3
- 6. SiluTDOWN C00f.ING SYSTEM ISOI.ATION 5
3
- a. Reactor Vessel Water Level-Low (Levell 6 .10, 11, 2 2 3, 4, 5 26 7 3)(2R21-N680 A, B, C, II) 12 -
u - ,
- b. Reactor Steam Dome Pressure-High 11 1 1, 2, 3 2R (2B31-N679 A, D)
4 -a a - 2 - : a . < < _ a a _ y -- - - - - , - - - , - - - - - - - - - - - - - TABLE 3.3.2-1 (Ceatieund) s ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours and in COLD SHUTDOWN-
. -e.s within the next 30 hours.
ACTION 2i - Be in at least.STARTUP with the main steam line isolation valves closed within 2 hours or be. in at least NOT-SHUTDOWN within 6 hours and in COLD SHUIDOWN witAin the next 30 hours. , . ACTION 22 - Be in at least STARTUP within 2 hours. "' ACTION 23 - Be in at least STARTUP with the Group 1 isolation valves closed within 2 hours or in at least ROT SRUTDOWN within 6 hours. ACTION 24 - V Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within one hour.
, ACTION 25 -
Isolate the reactor water cleanup system.
' ACTION 26 -
Close the affected system isolation valves and declare the affected system inoperable. ACTION 27 - Verify power availability to the bus at least once per 12 hours or close the affected system isolation valves and declare the affected system inoperable. ACTION 28 - Close the shutdown cooling supply and reactor vessel head spray , isolation valves unless reactor steam done pressure < 145 psis. t NOTES 4
# Actuates operation 'of the main control room environmental control I
system in-the pressurization mode of operation. Actuates the standby gas treatment system. When handling irradiated fuel in the secondary containment. a. See. Specification 3.6.3, Table 3.6.3-1 for valves in each valve group.
- b. A channel may be placed in an inoperable status for up to 2 hours for required surveillance without placing the trip system in the' tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
c. With a design providing only one channel per trip system, an inoperable ; channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall 4 be restored to OPERABLE status within .2 hours or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken,
- d. Trips the mechanical vacuum pumps.
- e. .
+ A channel is OPERAELE if 2 of 4 instruments in that channel are OPERABLE.
- f. May be bypassed with all turbine stop valves closed. l ,
- g. Closes only RWCU outlet isolation. valve 2G31-F004.
- h. Alarm only. ;
- i. Adjustable up to 60 minutes.
EATCH - UNIT 2 3/4 3-15 Amendment No. 7, 39
. _ , , , . . . - . ~ _ . _ . . _ . . ._
3/4.5 M?.GE!'CY CPM C00L1!!5 f.'.'!Tr*is i .
. ?/4.5.1' HICH in S5UP.E C00ffa!T I::K.C110'l'S STnt J. lit!Tn'G CO:!DITIQ:iTOR 0?f!!AT!O.'J .
3.5.1 Ti.c' High Pressure Coolant Injection (HPCI) s'ystem khal'1 ti
- OPEPht:LC uith:
( ..
- a. One OPETAELE high pressure ccclent injection pump, and . .
- b. An OPETABLE flew p:th capable of taking suction frem the suppression chember and transferring the water to the reactor pressure vessel.
*l.
APPLICAB_1LI'T'Y: CONDITIONS 1*, 2* and 3* with reactor vessel staan$ dome pressure > 150 psig. ACTION: . With the HPCI system inoperable, POWER. OPERATION may continue a. and the provisions of 3.0.4 do not apply *, provided the RCIC system, ADS, CSS and LPCI system are OPERABLE; restore the inoperable HPCI system to OPEPABLE status within 14 days or
- f be in at least HOT SHUT"0WN within the next 12 hours and
' reduce reactor steau deme pressure to i 150 psig within the* .-
- following 24 hours. .
With the rurveillcnca re;uirements of Specification 4.5.1 not b., perfemed at the requirta frequencies due to low reactor steta
- l pressure, the provisiens of Specificction 4.0.4 are not applic-able provided tbc cppropricte surveillance is performad within 12 hours after reactor cteam pressure is adec;ucte to perfom the tests.
- c. In the' event the HPCI is actutted and injects water into the reactor coolant system, c Special Rep:rt shall be prepared and -
- submitted to the Cc mitrien pursu:nt to Specific: tion d.9.2 within 90 days descri'oing the circu.r. stances of the actuation and the total accumulated actuations cycles to date.
S_URVEII.13.NCE REOUIP.D1El'TS - t
*Sce Special lest E.xception 3.10 5 .
3/4 5-1 taendi.v.:nt No. I 6 HATCil - U!i!T 2
* 'm-
.w . . .. .
EMIRGEllCY C0'.E C00 LING SYSTEMS . 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM LINTIM CONDITION FOR OPEPATION ak[ 3.5N The Automatic Depressurization System'(ADS) shall,be OPERABLE with at least seven OPERABLE ADS valves. APPLICABILITY: CONDITIONS
- 1. 2 and 3 with reactor vessel steam deme pressure >l50 psig. ,
ACTION:
- ~
- a. With one of the above required ADS valves inoperable. POWER OPERATION may continue provided the HPCI, CSS and LPCI systems are OPERABLE; restore the inoperable ADS valve to OPERABLE status within 14 days or be in at least NOT SHUTDOWN within the next 12 nours and reduce reactor vessel steam dome pressure '
to < 150 psig within the following 24 hours.
- b. .With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN ~ within 12 hours and reduce reactor steam dome pressure to < 150 psig within the next 24 hours.
- c. With the Surveillance Requirement of Specification 4.5.2.b not performed at the required interval due to low reacter steam pressure, the provisions of Specifkation 4.0.4 are not applicable provided the appropriate surveillance is perfomed 4
within 12 hours after reactor steam pressure is adequate to perform the tests. SURVEILLANCE REQUIREMENTS I D I i HATCH - UNIT 2 3/4 5-3 c'**--n e-- .e,-,v,gp,,,_ , _ _ _ _ _
, . ..EMERGENCY CORE C00LI[G $YSTEM5_ ,
~ ~
3 M.S.3 LOW DDESS'J I !O7E TOOLING SYSTE'S C: IRE SPRAY SYSTEM _ , , ' ILD*.* TING COND: TION FGR OPERATION 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:
- a. One OPERABLE CSS pump, and
- b. Nn OPERABLE flow path capable of taking suction fror. at least one of the following OPERABLE sources and trar.sferring the water through the spray sparger to the reactor vessel;
- 1. In CONDITION 1, 2 or 3, from the suppression pool.
- 2. In CONDITION 4 or 5*;
- a) From the suppression pool, or ,
b) When the suppression pool is being dr'ained, from the condensate storage tank containing at least (150,000) gallons of water. APPLICABILITY _: CONDITIONS 1, 2, 3, 4, and 5*. ACTION:
- a. In CONDITION 1, 2 or 3;
- 1. With one CSS subsystem inoperable, POWER OPERATION =ay continue provided both LPCI subsystems are OPERABLE; restore the inoperable CSS subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours and .in COLD SHUTDOWN within the following 24 hours.
- 2. ,With both CSS subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within next 24 hours.
- 3. In the event the CSS is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 90 days describing -he cir-cuestances of the a: uation and tr.e tc al ac:u-f a sc a.ctuation cycles t cate.
3 e r.: re .i-se ::
- ine core spray system and tne su::ression cnar:er an: :ne be OPERABLE provioed that the reactor vessel head is re ove:
cavity is flooded, the spent fuel pool gates are re ove:, aad tre water level is maintained within the. limits of Specificatic s 3.3.5 and 3.9.10 Arrendtrent 6 3'4 5-4 ',3. M "J_"" _ "U T 9 - - ,_,
e . lEME8.EEf CY CORE COOL!';3 SYSTEMS . LIMITING CONDITION FOR OPERATION (Continued) ACTIhN (Continued) .' .
- b. In CONDITION 4 or S*; ,
- 1. With one CSS subsystem inoperable, operation may continue provided that at least one LPCI subsystem is OPERABLE within'4 hours; otherwise, suspend all operations that have a potential for draining the reactor vessel.
- 2. With both CSS subsystems inoperable, operation may continue provided that at least one LPCI subsystem is
- OPERABLE and both LPCI subsystems are OPERABLE within 4 hours. Otherwise, suspend all operations that have a potential for draining the reactor vessel and verify that at least one LPCI subsystem is OPERABLE within 4 hours.
- 3. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS f l l 3/4 5-5 Amendment No. 6 HATCH - UNIT 2
7 EVERGENCY C0_RE C0OLING_,S_YSTEMS, N
< LOW PRESSURE COOLANT INJECTION SYSTEM LIMIT!NG CONDITION FOR OPERATION 4
3.5.3.2 lies independent Low Pressure Coolant Injection (LPCI) sub-systems of1the residual heat removal system (RHR) shall be OPERA 8LE with each subsystem comprised of:
- a. Two OPERABLE RHR pumps,
- b. An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water to the reactor pressure vessel.
APPLICABILITY: CONDITIONS 1, 2, 3, 4* and 5*, **. ACTION:
- a. In CONDITION 1, 2 or 3;
- 1. With one LPCI subsystem or one LPCI pump' inoperable.
POWER OPERATION may continue provided both CSS subsystems are OPERABLE; restore the inoperable LPCI subsystem or pump to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SRUT-DOWN within the following 24 hours.
'i
- 2. With both LPCI subsystems inoperable, be in at least NOT SHUTDOWN within 12 hours and either be in COLD SHUTDOWN or maintain reactor coolant temperature < 400*F by use -
of alternate heat removal methods within the following 24 hours.
- 3. With the LPCI system cross-tie valve open or power not removed from the valve' operator, be in at least NOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the following 24 hours.
i i 4. In the event the LPCI system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Comission L pursuant to Specification 6.9.2 within 90 days describ-Ing the circumstances of the actuation and the total accumulated actuation cycles to date. . j
- b. In CONDITION 4* or 5*, ** with one or more LPCI subsystems inoperable take the ACTION required by Specification 3.5.3.1.
The provisions of Specification 3.0.3 are not applicable. l
- Not applicable when two CSS suhr.ystuas are OPERABLE per Specification l
I 3.5.3.1.
**Not applicable when the (.55 is not required to be OPERABLE per 18 Specification 3.5..).l.
HATCH - UNIT 2. 3/4 5-1
-- _ . . , _ . . _ _ . .._.._._ . . _ . . . . _ _ . _ . _ _ . . _ . . _ . . _ _ _ _ , . , _ - . , _ . _ _ . . _ . . . ~ . . . . . . _ . , . -
~ ' ] ...- .
3/4.5.4 5UPPRE55704 CHA W , c: LIMIT 1h6 CONDIT1CN FOR OPEETION 3.5.4+The suppression chamber shal be OPERABLE with a minimu'm contateed water volume of 653,000 gallons, ecuivalent to a level of It?$". and the water level instrumentation channels alarms adjusted to actuste at a low water level 2,12'2", except that the suppression
- chamber may be drained: .
- a. In OPERATIONAL CONDITION 4 provided that;
- 1. No work is perforr.ed which has a potential for draining the reactor vessel,
- 2. The reactor m:de switch is locked in the Shutdown position, and 1
- 3. The core spray system is OPERASLI per Specification 3.5.3.1 with an OPERABLE flow cath capable of taking 4
svetion from the OPERABLE condensate storage tank and transferring the water through the spray sparger.to the
' reactor vessel.
- b. In OPERATIONAL CONDITION 5 previded that the reactor mode switch is locked in the Refuel position, and:
- 1. The core spray system is GPERA3LE per Specification 3.5.3.1 with an OPERABLE flow path casable of takir.g suction from i the OPERA 3LE condensate storage tank and transferring tne water through the spray sparger to the reactor vessel, or
- 2. The reactor vessel head is removed ar.d the cavity is flooded, the spent fuel pool gates are removed, ar.d the water level is maintained within the limits of Specifica-l
- tions 3. 9.3 2nd 3.9 10 ,
t CONDITION 1, 2, 3, 4 and 5.
.i APP!.lCABILITY:
ACTICN:
- a. In CON 0iTI0f; 1, 2 or 3 with t!e sue:ressien cham:er water level less than tne above limit, restore tne wa:er level to within the limit within 1 hour er be in at least HOT SHUTD0'.'N within the next 12 hours and in COLD SHUIDGiN within the following 24 hours.
- b. In CONDITION 4 or 5 with the suscression chamber drained and the conditions of Specification 3.5.4.a or 3.5.4.b. as -
4 apslicable, not satisfied, suspend all oserations in the reactsr vessel and all positive reactivity enar.ges. The provisiens cf Scecificatien 3.0.3 are not a alicatie. . l Amendment No, p, 35 W. CH - L':,IT 2 3/a 5 9 i .. . . . . . ... 7
Ev.I?.IEEY COT.E CC3* !!;G 5'?!TIMS
..c.
LIMITnCONDITION FOR OPERATION (Continued) ACTION (Continued) ,
- c. With one suppression chamber water level instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours and verify the suppression chamber water level to be > 12'2" -
at least once per 12 hours. . With both suppression chamber water level instrumentation l d. channels inoperable, restore at least one inoperable channel l to OPERABLE status within 6 hours or be in at least HOT SHUTDOWN , within the next 12 hours and in COLD SHUTDOWN within the following 24 hours and verify the suppression chamber water level to be
> 12'2" at least once per hour.
SURVEILLAN'CE REQUIREMENTS 3/4 S-10 Amendment N:. 6 HATCH - UNIT 2
'.- CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINER SYSTEMS .w - LIMITING CONDITION FOR OPERATION 3.6.6.2 Two independent primary containment hydrogen recombiner systems shall be OPERABLE. APPLICABILITY: CONDITIONS 1 and 2. ACTION
- a. With one hydrogen recombiner system inoperable, restore the inoper-able system to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours. The provisions of Specification 3.0.4 are not applicable.
- b. With both hydrogen recombiner systems inoperable, be in at least HOT SHUTDOWN within 12 hours.
SURVEILLANCE REQUIREMENTS I
-t UNIT 2 3/4 6-43
f / * *. X
+e Tattle 3. S4sperheated Steam 1-Aes Press.
W54 ta. Sat 54t. Temperature-De8ree5 Fahrenheit (sat. remel wa'er Steam 200 !$8 300 350 488 850 500 000 780 888 900 1806 1100 1200
'd g th 98 M I48 N 198 N 248 26 298 N 34626 398 M 898 M 598 M 698 M 19s 26 598 16 998 26 1090 76 e SA1614 331 6 392 5 422 4 452 3 482 8 Sit t 54t 7 571 5 631 1 600 7 750 3 set t este 979 8 9es 6
< i gg e h # 13 115 8 1150 2 1172 9 lt95 7 1218 7 1241 8 1265 8 1288 6 1336 8 1304 5 4433 7 les3 8 1534 9 15a6 8 16M 7 Z,, s 413N 1 9781 2 0509 2 0041 2 1152 2 1445 2.1122 2.1985 2 2237 22708 2 3144 2 3551 2 J134 2 4296 2 4640 2 4969 sh 37 16 8776 137 M 187 76 237 M 14776 337 76 43776 537 76 63716 73776 637 76 937}6 1037 16 I
e 0 01641 73 53 18 14 M23 90 24 9625 10224 10823 114 21 126 15 13808 150 01 161 94 173 06 185 78 19770 1162.248 h 13t20 till a 1148 6 1178 7 1194 8 1214 0 1241 3 1264 7 1288 2 1335 9 1384 3 1433 6 1483 7 1534 7 1506 7 1639 6 s 02349 1 9443 I 8116 I 9054 I 9360 1 9664 I 9943 2 0708 2 Gees 2.0H2 2 8309 2 1776 2 2159 2 2521 2 2064 2 3194
,, $b 6 79 54 79 106 79 1 % 19 206 79 256 79 306 79 406 79 506 79 00679 706 79 M679 906 79 1006 79 ggg37g3 e 0 01659 38 42 38 M 41 93 44 98 48 02 51 03 54 04 57 04 6303 89 80 74 98 80 94 86 91 92 87 90 84 h 161 26 1143 3 1146 6 1170 2 1193 7 1217 1 1240 6 1264 8 12878 1335 5 1384 0 1433 4 - 14835 1534 6 1586 6 1639 5 s 02836 1 1879 11928 88I?3 I 8593 1 8092 1 9173 1 9439 I M92 2.0ln 2M03 2.1011 2 1394 2IM7 2 2101 2 2430 14 des Sh 38 00 es 08 138 00 las 00 238 00 208 08 388 00 488 00 588 00 688 00 188 08 ass 00 948 00 e 0167 26 199 28 42 30 52 12 60 34 67 16 72 38 17 42 86 46 93 51 00 % 06 59 13 6319 67 h Gil091 e 18817 1150 5 1168 8 1192 6 1216 3 1239 9 4263 4 1287 4 1335 2 1383 8 la U 2 1443 4 1534 5 1586 5 1619 4 s Jill 1 7568 1 7833 1 8158 3 8459 I 8743 1 9018 1 9265 I 9739 2 0177 2 0505 2 0969 2 1332 2 1676 2 2005 15 Sh 3697 8697 13697 18697 2M 97 20697 30697 40697 58697 64497 186 97 80697 98697 e 0 01613 26 290 27 437 29 899 31939 33 % 3 35 917 37 905 41 986 45978 49 964 53 946 57926 68 905 65 R87 01383) h 18I21 1150 9 1168 7 1192 5 1216 2 1239 9 iM34 12872 1335 2 1383 8 1433 2 14834 iS34 5 1586 5 1639 4 s 0 3131 I M52 1 7809 18 34 1 8437 1 8720 1 8988 1 9242 1 9787 2 0l55 20%3 2 0946 2 1309 2 1653 t isa?
Sh ?? 04 ?? 04 127 04 1?? 04 222 04 272 04 372 04 472 04 572 04 67204 112 04 872 04 972 04 3 e 0 01683 20087 20 788 22 3 % 23 900 25 428 26 946 28457 31 466 34 465 37458 40 447 43 435 46 420 49 405 027 961 h 196 27 6456 3 16671 1891 4 1215 4 1239 2 1263 0 1286 9 1334 9 1383 5 1431 9 1483 2 1534 3 1586 3 1639 3 s 0 3358 8 1320 1 1475 1 7805 I 811I i 8397 186M i 8921 1 9397 I 9836 2.0244 2 0628 2 0991 a 1336 2lub 25 34 9 93 59 93 109 93 159 93 209 93 25993 359 93 45913 559 93 659 91 159 93 859 93 95991 e 0 01693 16 301 16 558 17 829 19 076 20 307 21527 22 740 25 153 27 557 29 954 32 348 34 740 37 130 39 518 . GM7) h 208 52 1160 6 11656 1190 2 1714 5 1238 5 1262 5 1286 4 1334 6 1383 3 1432 7 1483 0 1534 2 iS96 2 1639 7 s 435J5 1 7141 1 7212 1 547 1 78 % 1 8145 I Mil 1 8672 1 9149 1 9588 1 9997 2 0381 2 0744 2 !069 2 1418 Sh 49 66 99 66 14966 19966 249 66 349 66 649 64 549 E 649 66 749 66 849 64 949 66 M e 0 01701 13 744 14 810 15 v, 6 M2 1 914 18 929 20 945 22 %51 24 952 26 949 28 943 30 936 32 977 QS034) h 218 93 1164 1 IIM O 1213 6 237 8 2619 1286 0 1334 2 138J 0 1432 5 1482 8 1534 0 1586 8 1639 0 s 0 3682 1 6995 4 7334 1 7647 .1937 . 8210 18467 - 18%6 4 93e6 1 9795 2 0179 2 0543 20e88 2 1217 e e Sh 40 11 90 11 I40 71 190?! 240 11 340 71 440 71 540 71 640 71 740 FI 840 71 940 11 35 e 0 01708 11 8 % 12 654 13 562 14 453 15 334 16207 17 939 19 662 il 379 23 092 24 803 26 512 28 220 G59 29) h 228 03 1167 1 1147 8 1212 7 1237 P 1261 3 1285 5 1333 9 1382 8 1432 3 1482 7 1533 9 1586 0 16389
- t 0 3809 I 6812 1 7152 1 7468 I 7761 1 8035 4 4294 I 8774 1 9214 I 9624 2 0009 2 0312 2 0717 21046 Sh 32 15 82 n 132 75 I82 75 232 15 332 75 432 15 532 75 632 15 132 15 832 15 932 15 88 e 0 01715 10 497 110M 11 838 12 624 13398 14165 15 685 17195 18 699 20 199 21 697 23 194 24 689 0 62 251 h 2M le 1169 0 1186 6 1211 7 1236 4 1260 8 1285 0 1333 6 1382 5 1432 1 1482 5 1533 7 1585 8 1638 0 s 0 3921 1 6765 1 6992 1 7312 1 7608 1 7883 1 8143 1 8624 19065 1 9476 19860 2 0224 20569 2 0899 49 sh 25 56 75 % 125 % 175 % 225 % 325 % 425 % 525 % 625 % 725 % 825 % 925 %
(274 44) e 0 01721 1 399 9 777 10 497 il 201 11 892 12 577 13 932 15 276 16 614 IF 950 19 282 20 613 21943 h 24349 !!!21 1185 4 1210 4 1235 7 1260 2 12M 6 1333.3 1382 3 1831 9 1482 3 1533 6 1585 7 1638 7 s 0 4021 1 6671 1 6849 1 7173 11471 1 7748 8 8010 1 8492 1.8934 19345 1 9730 2 0093 2.0439 2 0768 38 St !$ 90 M 98 118 98 16890 21898 318 98 418 98 518 98 618 98 718 98 818 98 918 98 G8102) e 0 01727 8 514 8 769 9 424 13 362 80 688 11 306 12 529 13 741 14 947 16150 17350 18 549 19 746 h 250 21 1174 3 1184 1 1209 9 1234 9 1259 6 1284 1 1332 9 1382 0 1431 7 1482 2 1533 4 e585 6 1638 4 s 6 4112 66586 1 6720 1 7048 1 7345 1 7628 1 7890 18J74 1 8816 1 9227 1 9613 1 9977 2 0322 2 0652 55 Sh 12 93 62 93 112 93 162 93 212 33 312 93 412 93 512 93 612 93 712 93 81293 912 91 G87 #1 e 0 01733 7 945 8 546 9 130 9 102 10 267 il 381 12 485 13 583 14 677 15169 16 859 17 948 h 256 43 !!82 9 !?C# 9 1234 2 1259 1 1283 6 3332 6 1381 8 1831 5 1482 0 1533 3 1545 5 1638 5 s 0 4196 1 6601 1 6913 4 7237 I 1518 I 7781 8 82 % i 8730 t till I 9507 8 987 2 022 -20% Ge Sh 7 29 SF29 10729 15729 20729 30129 40729 50729 60729 101 29 807 29 90729 092 Fil e 0 01738 7 !?4 7 257 7 815 8 354 8 881 9 400 10 425 11 438 42 446 13 450 14 452 15 452 16 450 h 262 21 71176 1181 6 1208 0 1233 5 1258 5 12832 1332 3 1341 5 431 3 1481 8 1533 2 1585 3 1638 4 s 0 4213 1 6440 1 6492 1 6934 1 7134 1 7417 1 7681 I 8168 8 8612 1 9024 1 9410 t $174 2 0120 2 0450 Sh 2 02 $2 02 102 02 152 02 202 02 302 02 40202 502 02 602 02 702 02 80202 902 02 83 e 0 01743 6 553 6 675 7195 7697 8 106 SM7 9 615 10 552 ll 484 12 412 13 337 14 261 15183 G1I 883 h 267 63 1179 I 1180 3 12070 1232.7 12579 1282 7 1331 9 13813 1431 1 1481 6 1533 0 1585 2 163s 3 s 0 4344 8 6375 1 6390 I 6731 1 1040 1 7324 I M90 t 8077 I 8522 1 8935 I 9321 I 9685 2 0031 2 OJ6L Sh . 47 07 9707 14707 19707 29707 39707 497 07 59707 697 07 79707 89707 78 e 8 O!748 6 205 6 664 7 133 7 590 0 039 8 922 9 793 10 659 11 522 12 382 13 240 14 097 1302.931 h 212 74 1180 4 1206 0 1232 0 1257 3 1282 2 13316 1381 0 1430 9 1481 5 15329 1585 8 1638 2
- P 4411 1 6316 i M40 16951 1.1237 11504 1 1993 I 8439 I 8852 8 9238 1 9603 1 9949 2 0279 Sh 42 39 92 39 142 39 19239 292 39 39239 492 39 592 39 692 39 792 39 89239 75 e 0 01753 5 814 6 204 4 645 7074 7 494 8 320 9 135 9 945 to no 11 553 12 355 L31%
1307 61) h 27756 1181 9 1205 0 1231 2 1256 7 1288 7 1331 3 1300 7 1430 ? 1481 3 1532 7 1585 0 1638 I s 0 4474 1 6260 1 6554 1 6864 171% 1 7424 1 7915 1 8361 1 8774 1 9161 1.9526 1 9872 2 0202 h = enthalpy, Stu per Ib l Sh = superheat, F y = Specific volume, tu ft per Ib s = entropy, Stu per F per Ib _l w
'w, - - . .
l l
p - p , 5 Tattle 3. Superheated Steam-Coseefseased gag 3,g Temperature -Degrees f ahrenheit ($4t. Tevne) Water $ team 310 4N 450 SN ' 550 W 2W W W IM 11 5 12W IM les p Sh 37 % 87 M 13796 14796 23796 287 N 387 M 487 M to7 M 887 M 187 96 5796 987M 1987 96
. 79 e 408757 5 471 S ul 6 214 6 622 7 018 7 488 7 794 8560 9 319 64 475 10 029 11 541 12 333 13 ml 13 829
- @ 98204 h 20215 1183 1 1204 0 12M 5 1256 8 1281 3 135 2 13M S 13m 5 143 5 1448 1 1532 6 1544 9 1618 0 lett e 17468 s 8 4534 16N8 1 6473 1 6790 1 7000 1 7349 I M02 1 7942 1 8289 1 8702 19W9 1 9454 19mt 2 0134 2 0446 2 0150 1h 33 14 83 14 133 74 183 74 233 74 283 74 383 74 483 74 583 74 683 74 783 74 883 74 983 74 1083 74 m e 00lM2 5167 5445 5 840 6 223 6 597 6 966 7 330 8 052 S MS 9 408 10 190 10 808 ti me 12 310 13014 (316261 h 206 52 lies 2 1203 0 1229 7 IM55 1280 8 1305 8 1338 6 135 2 1438 3 1481 8 1532 4 1584 7 1637 9 1991 9 1746 8 s 0 4590 16L59 1 6396 1 6716 1 7000 1 7219 1 7532 11772 1 8220 186M 1 9871 1 9306 1 9733 2 0063 2 0379 2 0642 5h 29 72 19 ?! t2912 179 72 229 72 279 ?? 379 72 479 ?? 579 72 679 12 ??9 ?? 879 ?? 979 72 1079 ??
9e e 0 017 % 4 895 5 128 5 505 5 869 6 223 6 572 6 917 7600 8 277 SMO 9 621 10 290 10 % 8 11 625 12 h6 02029 h 290 69 lin 3 1202 0 12289 1254 9 1280 3 1305 4 1338 2 13e00 1430 8 - 1480 8 6532 3 1544 6 1637 8 1691 8 1744 7 s 0 443 I 6113 1 6323 1 6646 1 6940 1 1212 1 7467 I 7757 I 8156 I 8570 l8M7 1 9323 ' I 9669 2 0000 24316 2 0619 Sh 2587 75 87 17547 17587 22547 2587 JN87 4587 57587 67587 77587 875 87 975 87 1075 87 M e 0 01770 4 651 4 845 5 205 S MI 5 809 6 221 6 548 75% 1834 e 477 9 133 9 747 10 Ja0 11 017 11641 1324 t 3) h 214 70 1886 2 L2009 1228 1 1754 3 1279 8 1305 0 13299 1379 7 14?9 9 1480 6 15321 1584 5 16J7 7 1691 7 1746 6 s 0 4694 86069 I 6253 1 6500 16876 4 1149 8 7404 1 7645 1 4094 I 8509 1 8497 8 9262 1 9609 I 9940 2 02 % 20%9 Sh 2218 7218 12218 47218 22218 272 18 37218 41214 57218 61218 77218 87218 972 !8 107218 la v 0 01774 4 431 4 590 4 935 52M 5 588 5 904 6 216 6 833 7 443 8 054 86% 9 258 950 10 460 11 060 1327 821 h 290 54 1187 2 1199 9 1227 4 1253 7 1279 3 1304 4 1329 6 1319 5 1429 7 14e 4 1532 0 1584 4 16376 1691 6 1746 5 s 04143 1 60?? I 6187 I 6516 I 6814 I 7084 5 1344 11586 4 8036 I 8458 8 88N I 9205 I9%2 1 9083 2 0199 2 0502 Sh 18 63 6463 188 63 864 63 218 63 268 63 368 63 468 63 % 8 63 644 63 M863 864 63 968 63 1068 6'3 - 195 e 0 01778 4 231 4 359 4 690 5 007 5 315 5 617 5 915 6 504 7 006 7 e65 8 241 8 814 9 309 9 961 10 532 13313h h 302 24 115 0 1898 8 1226 6 1253 1 1278 8 1304 2 1329 2 13792 1429 4 143 3 1535 8 1584 2 1637 5 1691 5 17464 s 0 4190 1 5988 1 6122 1 64 % 1SMS I 1031 1 7288 i M30 4 1981 183M I 8785 8 1158 I 9498 I 9028 2 0145 2 0448 Sh 1521 652t 18521 165 21 215 21 26521 365 2t 465 21 % 521 66521 76521 865 23 9652t 1065 21 lit e 0 01782 4 048 4149 4 48 4 772 5 068 5 357 5 642 6 205 t ill 7 314 7 865 8 413 8 968 9507 80 053 0 34 191 h 305 00 1188 9 1197 7 1725 8 1252 5 1778 3 1303 8 1328 9 1379 0 1429 2 443 1 1531 7 1544 1 1637 4 1691 4 1746 4 s 0 4834 L 5950 1 6068 I 6396 i H98 1 6975 11233 1 1476 1 1928 I 8344 I 8732 8 90H I 9444 1 9717 2 0093 2 0397 Sh ll 92 6192 III 92 161 92 21] 92 261 92 361 92 461 92 561 92 661 92 Mt 92 861 92 961 92 1961 92 Ill e 0 01785 38e1 3M7 4 265 4 558 4 841 Sitt 5 392 5 932 6 465 69M 7 528 8 046 8 570 9 093 9 615 0 38 001 h 309 25 1189 6 1896 7 1225 0 1251 8 1277 9 1303 3 1328 6 137t1 1429 0 1479 9 1531 6 1584 0 1637 2 lett e 1746 3 s 0 4477 15913 I 6001 I 6340 I 6644 I 6922 8 7181 11425 11071 1 8294 I 8682 1 9049 I 9396 I 9727 2 este 2 0347 s e *
- 56 4 73 58 13 108 13 158 73 208 73 4258 73 354 73 454 73 % 8 13 658 13 158 73 858 73 958 73 1058 13 129 s 0 01789 3 1775 3 1815 4 07S6 4 3610 4 6341 4 9009 51637 5 6413 61928 6 7006 72060 7 7096 8 2119 8 7130 92 34 0412h h, 312 58 1190 4 1195 6 1224 8 1251 2 12774 1302 9 1328 2 1378 4 1428 8 1479 8 1531 4 !583 9 16311 1691 3 1746 2 s 049t9 L 5879 I 5943 I 62M i 6592 1 6872 1 7132 1 1376 1 7829 I 8246 8 8635 1 9001 1 9349 ' I 9600 t 9996 2 0300 Sh 267 5267 10267 15267 202 67 25267 35267 45267 552.67 65267 75247 852 67 95267 1052 67 138 e 0 01796 34544 3 4699 3 7489 4 0129 4 2672 4 5151 4 7589 5 2344 5 7118 title 6 6446 F il40 15781 8 0418 85033 047331 h 318 95 1191 1 1893 4 1222 5 1249 9 1276 4 1302 8 1327 5 1377 9 1428 4 14794 1531 1 !$43 6 1636 9 1698 8 17468 s 0 4998 I 5813 1 5833 8 6182 1 6493 1675 I 7037 11243 1 1737 I 81 % 1 8545 I 89tI tSnt i 9591 1 9907 2 0211 Sh 46 96 96 96 144 % 1 % 96 248 M 346 96 444 % Set 96 646 96 746 96 SM M 946 96 1046 96 14e e 0 01803 3 2190 34H1 31143 3 9526 41844 4 4119 4 8588 5 2995 5 7364 6 1709 6 6036 70349 74652 7 8946
'353 04) h 324 % 1193 0 1220 8 1248 7 1275 3 1301 3 1326 8 13774 1828 0 1479 8 1530 8 1583 4 1636 7 1690 9 1745 9 s 0 5071 1552 1 6085 1 6400 t M86 16949 ' I 71M I 7652 1 807I I 8461 1 8028 I till I 9508 1 9875 2 0129 sn 4157 9157 14157 19157 24157 341 57 44857 54157 64157 74157 841 51 948 % 1041 %7 158 e 0 01809 3 0139 3 2208 1 45 % 36799 3 8978 4 :112 4 5298 4 94?l S J507 5 7564 6 1612 6 % 47 69%I 7 ht!
'352 43: n 110 65 1194 1 1219 8 1247 4 (274 3 1300 5 1326 8 1316 9 1427 6 1878 7 1530 5 1583 8 1616 5 IM07 174i 1 s 0 514I IW5 1 5493 1 631) 1 6602 16867 17 15 1 573 1 7992 58381 18751 1 9099 l 9411 1974n 2 0052 Sn 16 45 8445 136 45 186 45 236 45 33545 436 45 53645 63645 136 45 83645 9h 45 to16 as 158 e 0 01815 2 03M 1 0060 3 2/88 - 1841) 36469 3 8480 4 7420 46295 5 0132 5 3945 5 7741 61522 65?93 6 90 %
041 %i
- 336 07 fl951 1217 4 1286 0 !?73 3 1299 6 :325 4 1376 4 1427 2 1478 4 1530 3 1582 9 16h 3 1640 5 1745 6 s 0 5206 1 5648 1 5906 1 6231 1 6522 16790 1 1039 1 7499 1 1919 1 8310 l 8678 i 9027 I 9359 i % 76 I 9980 Sa 31 58 81 58 13158 18854 23158 331 58 431 54 531 58 63t 58 731 54 831 54 9J158 1038 58 178 e 0 01821 26738 2 8162 3 02s3 3 2306 3 42 % 3 6158 3 9879 4 3536 4 71 % 50749 54325 5 7888 6 1440 6 4943 (M4423 h 34124 11 % 0 1215 6 1244 7 1272 2 1294 8 1324 7 1375 8 1426 8 1478 0 15300 If 92 6 1636 8 1690 4 17454 s 0 5269 1 % 91 1 5823 8 6152 16447 1 6717 1 6968 17428 1 7850 I 8241 1 8610 1 4959 I 9291 8 9608 I 9933 Sh 26 92 76 92 826 92 176 92 226 92 3'6 92 426 92 526 92 626 92 726 92 826 12 976 92 1026 92 la v 0 01827 2 5312 2 6474 2 8508 3 0433 3 2286 3 4093 3 7621 4 1084 4 4508 4 7907 51289 5 4657 5 8014 6 1363 0 73081 4 34619 !!96 9 1213 8 1243 4 1211 2 1297 9 1324 0 1375 3 1426 3 1477 7 1529 7 1582 4 1635 9 1690 2 17453 s . 0 5328 1 % 43 t 5743 1 6018 I 6376 i M47 I 6900 tFM2 1 7754 I 8176 I 8545 1 8094 t 9227 8 9545 I 9849 sh 2247 7247 12247 17247 22247 32247 42247 52247 622 47 72247 82247 922 47 1022 47 III e 0 01833 1 4030 24%I 2 6915 28756 3 0525 3 2246 35601 3 8809 4 2140 4 5365 4 8572 51766 54949 5 8124 07753) h 350 94 #1974 1212.0 1242 0 1270 1 12973 1323 3 1374 8 1425 9 14774 1529 4 1582 1 1635 7 1690 0 1745 1 s 0 5384 1 5498 I % 67 1 6006 1 6307 I 6581 1 6435 8 1299 I 7722 1 8115 i Saae 1 8434 Itiu 9444 1 9789 Sh 18 20 68 20 118 20 168 20 218 20 3I8 20 418 20 518 20 618 20 718 20 81820 918 20 1018 20 35 a 4 01829 2 2873 2 3598 2 5480 2 1247 2 8939 3 0583 3 3783 3 6915 4 0004 4 3071 4 6128 4 9165 5 2191 5 5209 0 81 801 h 355 51 1198 3 1210 1 1240 6 1269 0 1296 2 1322 6 1374 3 1425 5 14170 1529 I 1581 9 1635 4 1609 8 t1450 s 0 5434 8 5454 1 5593 4 5914 1 6242 I 6518 1 6773 1 1239 1FM3 I 8057 I 8426 8 8776 I 9809 I 9427 I 9732 Sh - Superheat.F h = enthalpy, Btu per Ib v = specibe volume, tu tt per Ib 5 = entropy, Stu per F per Ib s
E n' Table 3. Superheated Steam-Continued Aes Press-
~ to. Sat $4t. Tem 0erature -DeBree5 Fahrentml
~
(Saf eunti- Water Steam 400 450 500 $$8 000 700 Ist 900 1000 1100 3200 1380 1400 1508
'. Sh 14 09 64 09 114 09 164 09 fle et 314 09 414 09 514 09 614 00 714 09 814 09 914 09 1014 09 1114 09 9 110 - e 0 91844 2 1822 2 2364 2 4181 2 5400 2 7504 2 9018 32137 3 5128 3 a000 41007 4 3915 4 6411 49H5 5 2571 5 5440 Wil n . 359 91 1199 0 1208 02 1239 2 1268 0 1295 3 1321 9 1373 7 1425 1 1476 7 1528 8 1541 6 1635 2 1649 6 1744 8 1800 8 9 0 5490 1.5413 4 5522 1 5472 8 6180 16458 8 6715 11182 1 7607 I 8001 1 8371 18721 1 9054 1 9372 1 % 77 8 9970 i
Sh 1012 6012 110 12 160 82 21012 31012 410 12 510 82 41012 11012 8'012 91012 1010 12 1110 12 380 v 6 01850 ' 2 0063 2 1240 22999 2 4634 2.6199 2 Hl0 3 0642 3 3504 J 6327 3 9125 4 1905 4 % 71 4 7426 5 0173 5 2913 (30988 h 364 17 1899 6 1206 3 1737 8 1296 9 1294 5 1321 2 1373 2 1424 7 1476 3 1528 5 1541 4 1435 9 16sB 4 1744 7 1800 6
-s 05540 1 5314 1 5453 I 5408 1 6120 t 6400 1 6654 81828 1 7553 1 1948 I 831a I8%8 1 9002 I 9320 8 9625 I 9919 54 6 30 % 30 106 30 1 % 30 206 30 306 30 406 30 506 30 606 30 706 30 806 30 906 30 1006 30 1106 30 230 3 0 01855 1 9905 2 0212 21919 2 3503 2 5008 2.6461 2 9276 3 2020 34726 3 7406 4 0068 427t7 4 5355 4 7984 5 0606 (393 101 h 36428 1200 1 1204 4 1236 3 1265 7 1293 6 1320 4 1372 7 1424 2 1476 0 1528 2 1581 1 1634 8 16a9 3 1744 5 1800 5 s 0 5584 1 5336 1 5385 1 5747 1 6062 1 6344 1 6604 1 7075 1 7502 13897 1 8268 1 8618 1 8952 1 9270 1 9576 1 9669 Sh 268 52 61 102 61 152 61 202 61 302 61 402 6I 502 61 602 61 702 61 802 61 902 61 1002 61 1102 61 2e8 e 0 01860 1 9177 1 9268 2 0928 2 2462 2 3915 2 5316 2 s024 30661 33259 3 5831 3 8385 4 0926 4 34 % 4 59n 4 8492 (391 396 h 37227 1200 6 1202 4 1234 9 1264 6 1292 7 1319 7 1372 8 1423 4 1475 6 1527 9 1580 9 1634 6 1689 1 1744 3 1800 4 s 0 5634 8 5299 1 5320 15647 4 6006 14291 1 6552 11025 t 7452 1 1848 l-8219 I 4570 1 8904 8 9223 1 9528 8 9822 Sh 4903 99 03 149 03 199 03 299 03 399 03 499 03 599 03 699 03 199 03 899 03 999 03 1099 03 290 v 0 01065 1 8432 2 0016 2 1504 2 2909 2 4262 2 6412 194to 31909 3 4382 36837 3 9278 4 1709 4 4131 4 6546 (400 97) h 376 14 1201 1 1233 4 1263 5 t2918 1319 0 13716 1423 4 14753 1527 6 1540 6 1634 4 16a8 9 8744 2 1300 2 s 0MTS l 5264 1.5629 1.595I I 6239 I 6502 4 6976 I 7405 1 1801 1 8173 8 8524 8 8850 1 9117 I 9482 1 9776 Sh 45 % 95 56 145 % t95 % 295 56 395 54 495 56 595 % 695 56 795 56 895 % 995 56 1095 %
le v 0 01170 1 7742 1 9173 2 0619 21901 23299 2 5808 2 8256 3 0663 3 3044 3 5400 3 7758 4 0097 4 2427 4 4750 (404 441 h 379 90 1201 5 1231 9 1262 4 1790 9 1318 2 1311 1 1423 0 1474 9 1527 3 1540 4 1634 2 1648 7 1744 0 1800 1 s 0 5722 1 5230 1 5573 1.5899 I 6189 i 6453 1 6930 I 1359 1 77 % I 8128 I 4480 t est4 1 9133 8 9439 l 9732 Sh 4220 92 20 14220 192 20 292 20 392 20 492 20 592 20 692 20 19220 89220 992 20 1092 20 238 v 6 01875 1 7101 1 1391 1 9799 2 1121 21388 2 4824 2 7186 2 9509 3 1306 3 4084 36343 3 3603 4 0849 4 3047 1487am h 383 % 1201 9 1230 4 1261 2 1290 0 1317 5 1370 5 1422 6 to74 6 1527 1 1540 I I634 0 1688 5 1743 9 1000 0 s 0.5764 I 5197 1.5518 1.5848 16140 I 6406 1 6085 t1315 l 7783 I 8085 I 8437 1 477I I 9090 1 9396 I 9690 54 3493 88 93 I38 93 188 93 288 93 388 93 488 93 548 93 Gas 93 788 93 888 93 908 93 1008 93 M e 0 01000 1 6505 1 7665 1 9037 2 0322 2 1551 2 3909 2 6194 2 8437 3 0655 32855 3 5042 3.7217 3 9384 . 4 1543 (41107) h 38712 1202 3 1228 8 1260 0 1289 1 1316 8 1370 0 1422 1 1474 2 1526 8 1579 9 1633 8 1648 4 1743 7 1799 8 s 0 5805 1 5166 1 5464 1 5798 1 6093 1 5361 1 6841 1 7213 11671 1 8043 1 8395 18730 1 9050 1 9356 1 9649
% .mme % ===
. Sh 35 75 85 75 135 75 185 75 285 75 385 75 485 75 585 15 685 15 785 75 845 75 985 75 1005 75 295 v 0 01885 15948 I 6988 18327 8 9578 2 0772 2 3058 25269 2 7440 2 9585 31718 3 3424 3 5926 3 8019 4 0106 (414 251 h 390 60 !?o26 1227 3 1258 9 1798 1 1316 0 1369 5 1421 7 14739 1526 5 1579 6 1633 5 16a82 1743 6 1799 7 s 0 5844 1 5135 1.5412 1 5750 1 6048 1 6317 1.6799 1 7232 1 7630 1 8003 1 8356 1 8690 1 9010 1 9316 1 % 10 54 32 65 82 65 13265 182 65 282 65 382 65 482 65 542 65 68265 782 65 382 65 982 65 1082 65 300 v 0 01889 1 5427 1 63 % 1 7665 1 8883 2 0044 2 2263 2 4407 2 6509 2 8585 3 0643 32608 34721 3 6746 3 8764 del 7356 h 393 99 1202 9 1225 7 1257 7 1287 2 1315 2 1368 9 1821 3 14134 1526 2 1519 4 1633 3 1608 0 1143 4 I199 6 s 0.5882 1 5105 1.5361 15703 I 6003 1 6274 5 6758 I 1892 1 7598 1 7964 I 8317 I 8652 1 8972 1 9278 I 9572 Sh 29 64 79 64 129 64 179 64 279 64 379 64 41944 579 64 679 64 779 64 879 64 979 64 1079 64 31 8 0 01094 3 4939 I 5763 1 1044 I 8233 1.9M3 21520 2 3600 2 5638 2 1650 2 9644 3 1625 3 3594 3 5555 3 7509 1420 36) h 39730 12032 1224 1 1256 5 1296 3 1314 5 1368 4 1420 9 14732 1525 9 15792 1633 8 16878 1743 3 1799 4 s 0 5920 1.5076 1 5311 1 5657 1 5960 1 6233 1 6719 1 7153 1 7553 1 7927 1 8280 1 8615 1 8935 1 9241 1 9536 Sh 2669 76 69 126 69 176 69 276 69 37' 69 476 69 576 69 676 69 776 69 87669 976 69 1076 69 329 e 0 01899 1 4480 15207 1 6462 1 7623 1 8725 2 0823 2 2843 2 4a21 26714 28704 3 0628 3 2538 3 4438 3 6332 I423 3tt h 400 53 1203 4 1222 5 1255 2 1285 3 1343 7 1367 4 1420 5 1472 9 1525 6 1578 9 1632 9 1647 6 1743 1 1799 3 s 0 5956 1 5048 1 5268 3 5612 15918 1 6192 L 6680 t Fil6 1 1516 1 1890 4 4243 1 8579 1 8s99 192'IE I 9500 54 2382 73 82 123 82 173 82 273 82 37381 473 82 513 82 67382 773 87 873 82 97382 107382 338 v 0 01903 1 4048 1 4644 1 5915 1 7050 1 8125 2 0168 2 2132 2 4054 2 5950 2 7828 2 % 92 3 :545 3 3349 35227 1426 186 h 403 70 1203 6 1220.9 1254 0 1284 4 1313 0 13673 1420 0 14725 1525 3 1578 7 1632 7 16875 1742 9 17992 s 0 5991 1 5021 1 5213 1.5%8 I 5476 1 6153 I 6643 1 7019 1 1480 1 1855 1 8208 8 8544 I 8864 L 9171 I 94 %
Sh 21 Ot 71 61 121 01 17101 271 01 37101 471 01 57101 671 01 171 01 871 01 971 O! 1071 01 348 v 0 01908 1 3640 1 4191 1 5399 1 6511 1 7561 1 9552 21463 2.3333 25t75 2 7000 2 8811 3 0611 3 2402 3 4106 (428 99I h 406 30 12038 1219 2 1252 8 1283 4 1312.2 1366 7 1419 6 1472 2 1525 0 1578 4 1632 5 16473 1742 8 1799 0 s 0 6026 14994 1.5165 1.5525 1 5836 16114 1 6606 1 7044 1 7445 1 7820 1 8174 1 8510 1 8431 1 9138 1 9432 Sh 1827 6827 11827 168 27 26827 36827 468 27 M427 66827 764 27 368 27 968 27 1068 27 als e 0 01912 1 3255 1.3725 14913 1 6002 1 7028 1 8970 2 0832 2 2652 2 4445 2 6219 2 7900 29730 31471 3 3205 (431 733 h 409 83 1204 0 1217 5 1251 5 1282 4 1311 4 1366 2 1419 2 1471 8 1524 7 1578 2 1632 3 1687 1 1742 6 1798 9 s 0 6059 14968 1.5119 1 5443 1 5797 1 6077 16571 1 7009 1 7411 1 7787 1 8141 1 8477 1 8798 1 9105 1 9400 Sh 1559 65 59 115 59 65 59 26559 36559 44559 565 59 66559 165 59 865 59 965 59 1065 59 W v 8 01917 12891 1 3285 1 4454 15521 .6525 1 8421 20237 2.2009 2 3755 2 5482 2 7t96 2 8898 3 0592 3 2279 (434 ell h 412 81 1204 1 1215 8 1250 3 1281 5 310 6 1365 6 1418 7 1471 5 1524 4 15779 1632 1 1686 9 1742 5 1790 a s 0 6092 14943 1 5073 1 5441 4 5758 .6040 16536 3 6976 8 7379 1 1754 I 8109 1 8445 i Site 1.9073 8 9368 Sh 10 39 60 39 .10 39 160 39 260 39 360 39 460 39 560 39 66039 760 39 860 39 960 39 1060 39 let 0 01925 1 2218 1.2472 1 3606 .4435 1 5598 1 7410 1 9139 2 0825 2 2484 2 4124 2 5750 2 7366 2 0973 3 0512 (431 616 h 41859 1204 4 1212 4 1247 7 279 5 1309 0 1364 5 1417 9 1470 8 1523 8 15774 1631 6 1686 5 1742 2 1798 5 s 0 61 % 1 4894 1 4982 1 5360 !5683 1.5969 1 6470 1 6911 1 1315 1 7692 l 8047 1 8384 I 8105 I 9012 1 9307 Sh = Superheat. F h = enthalpy. Btu per Ib v = 5pecif t volutne, cu ft per Ib 5 = entropy. Btu per F per Ib G
y k *
. r:. L z : 0 =; -. . : = - _.,_ _ : m m = m ~
2 Table 3. Superheeted Steam-Continued
. 'Aos Prves. Temperatwe-De8rees F4hrenheit la $4t. $4t.
64 water Ste4e 458 500 550 008 850 200 800 900 1000 1100 1200 1305 1400 1500 y J ;; ih
- f. ; /4 4 th
-e 540 5540 105 40 15540 20540 255 40 355 40 45540 % 5 40 655 40 M540 855 80 M540 10% 40 8 01934 1 1610 11738 12841 1 3836 14763 1 % 44 1 6499 1 8151 19759 21339 2 2901 2 4450 25907 2 M15 29037
*;9W'~ " ' t 42417 1204 6 1208 8 1245 1 12775 1307 4 " 1335 9 IM34 14 t 7 0 1470 1 1523 3 1576 9 1631 2 1686 2 L74t t 1798 2
. M, s 06217 I 4847 1 4494 1 5282 8 5611 1 5901 4 6163 1 6406 3 6850 t 1255 t 1632 1 1988 I 8325 t 8647 l 8955 l 9250 9 60 50 60 100 60 50 60 200 60 250 60 350 60 450 60 550 60 650 60 750 40 850 60 MO 60 1050 60 418 e 0 01982 11057 - 1 1071 1 2148 1 3113 4007 1 48 % 1 % 76 1 7258 1 8795 2 0304 21795 2 3273 24739 2 6196 2 1647 Mel45 h 421 % 1204 7 1205 2 '1242 4 1254 305 8 1334 5 1362 3 4416 2 1449 4 1522 7 1576 4 1630 8 1685 4 t74t 6 1798 0 5 0 6276 34802 14904 1 5206 1 5542 5835 I 6100 t 6345 1 6791 1 7197 1 1575 1 7137 4 8269 1 8591 1 8899 I 9195 54 4597 9591 18597 19597 24597 345 97 44597 54597 64597 74597 88597 14597 1045 97 448 e 0 01950 1 0554 18517 1 2454 1 3319 1 4138 1 4926 1 6445 1 7918 19M3 70790 2 2203 2 3605 24998 2 6384 (454 03) h 434 77 1204 8 1239 7 12734 1304 2 1333 2 1361 t 1415 3 1468 7 1527 t 1575 9 1630 4 1685 5 1741 2 17977 s 0 6332 I 4759 1 5132 1 5474 15772 1 6040 1 6286 16734 17t42 1 521 1 7878 4 8216 1 8134 18847 t il43 54 41 50 91 50 14150 191 50 241 50 341 50 441 50 541 50 641 50 .741 50 841 50 941 50 1041 50 W e 0 01959 1 0092 1 0939 1 1852 1 2691 1 3482 1 4242 1 5703 17tl7 1 8504 1 9872 21226 22%9 2 N03 2 57Jo (4 % 59 h 439 83 1204 8 12M 9 4271 3 1302 5 1331 8 1360 0 1414 4 1468 4 152t 5 1575 4 . 1629 9 1685 1 1740 9 17914 s 06387 14718 1 5060 1 5409 1 5111 1.5982 1 6230 1 6680 B.7(A9 1749 1 7826 1 8165 1 8444 18797 1909J Sh 3718 8718 13718 187 t8 23718 33718 43718 53718 63718 737 18 83718 93718 1037 18 48 e 0 01967 09E8 104c9 1 1300 12t15 128t! 1 3615 1 5023 16384 1 7716 1 9030 203JO 216ft 2 2100 2 4f 73 1462 829 h 444 75 1204 4 1234 1 1269 1 1300 8 1330 5 1358 8 1413 6 1467 3 1520 9 1574 9 1629 5 1684 7 1740 6 17972 s 0 6439 I 4677 I 4990 1 5344 1 % 52 1 5925 l 6l76 16628 1 7038 8 1419 1 7777 I Sill I 8439 1 8748 1 9045 Sh 32 99 82 99 132 99 182 99 232 99 332 99 432 99 532 99 632 99 732 99 83299 932 99 1032 99
- tu o 0 01975 0 9276 0 9919 10791 11584 1 2327 1 3037 18397 1 5708 1 6992 182% 19507 2 0746 21977 2 3200 (467 011 a 44952 1204 7 12312 1267 6 1799 I 1329 I 1357 7 1412 7 leu 6 1520 3 1574 4 1629 t 1684 4 1740 3 1196 9 s 0 6490 l 4639 1.4921 1 5284 I 5595 1 5871 l 6123 1 6578 1 6990 1 7311 1 7730 1 8069 I SJ13 18702 i 8998 Sh 28 93 78 93 ]2g g3 [7893 22893 328 93 428 93 52893 62893 128 93 828 93 92893 1028 93 13 e 0 01982 0 8914 0 9464 1 0321 B 1094 1 1816 1 2504 13819 1 5085 16323 1 7542 1 8146 1 9940 21175 2 2302 44 71.075 h 454 I8 1204 5 1228 3 1764 8 1297 4 1327 7 t356 5 14iL 8 1465 9 1519 7 1573 9 1628 7 1684 0 1740 0 t 796 7 s 06540 4 4601 1 4453 1 5223 I 5539 1 5818 1 6072 1 6530 1 6943 I 7325 l 1684 I 8024 3 8344 I 8657 I 8954 Sh 24 99 74 99 124 99 174 99 224 99 324 99 424 99 524 99 624 99 124 99 824 99 924 99 1024 99 948 e 0 01990 0 8577 0 9045 0 9884 1 0640 1 1342 1 2010 8 3284 1 4508 1 5704 1 6880 1 8042 19113 2 0336 f l47f c4710!! h 458 71 1204 4 1225 3 1262 5 1295 7 1326 3 1355 3 1410 9 1465 8 1519 1 1573 4 1628 2 1683 6 1739 7 1796 4 s 06587 4 4565 14736 1 5164 4 5485 15767 1 6023 1 6483 I 6897 L 7280 t 1640 1 1981 1 8305 t 8615 I 898 t
' Sh 2116 1116 12116 17116 22t 16 321 16 421 16 521 16 62116 12I 16 82116 921 16 1021 16 188 e 0 01998 0 8264 0 8653 09479 1 0217 4 0902 1 1552 12787 1 3972 1 5129 16766 1 7148 1 4500 19603 2 0b99 4478 441 h 46314 1204 2 1222 2 1260 3 1293 9 1324 9 1354 2 1410 0 1864 4 1518 6 1572 9 1627 8 1683 3 4739 4 11% I s 0 6634 4 4529 I 4720 t 5106 I 543L I 5717 1 5975 1 6438 8 6853 4 1237 1 7598 1 1939 1 8263 1 8573 1 8870, Sh 1743 6743 11743 16743 21743 31743 4tI43 51743 61743 71743 81743 91743 101743 58 e 0 02006 0 7971 0 8287 0 9100 0 9424 1 0492 1 1125 1 2324 13473 14593 15693 1 6780 8 7855 1 8921 1 9980 1481 57) h 46747 1203 9 1219 1 8258 0 1292 1 1323 4 1353 0 1409 2 1463 7 1518 0 1572 4 1627 4 1682 9 1739 1 1795 9 s 0 6679 I 4495 I 4654 1 5049 I 5380 ISMS I 5929 I 6J94 1 681I I F196 1 15 % 11898 I 8223 I 8533 I 8831 Sh 13 80 6380 113 80 163 80 213 80 313 80 41380 513 80 613 80 713 80 813 80 913 80 10t3 80 85 s 0 020t1 0 7697 0 7944 0 8746 0 94 % 1 0109 1 0726 1 1892 t 3008 1 4093 1 5160 1 6281 8 7252 1 8284 1 9309 1452S n 471 70 1203 7 1215 9 1255 6 1290 3 1322 0 IJ518 I408 3 18630 15174 1571 9 16270 168? 6 1738 8 IMs4 5 ^ 06723 1 4461 1 4590 14993 1 5329 1 5621 1 5884 1 6351 1 6769 t il55. 17517 1 7859 1 8184 1 8494 1 8192 Sh 511 55 11 105 11 155 11 205 11 305 11 405 18 505 11 Gas tl 105 11 805 11 905 1 1005 11 658 e 0 02032 0 7084 0 1173 07%4 0 8634 0 9255 0 9835 8 0929 11969 12979 13%9 14944 1 5909 1 6864 t /stJ 1494 891 h 48189 1202 8 1207 6 1249 6 1285 7 1318 3 1348 7 1406 0 1461 2 t$15 9 1570 7 1675 9 1641 6 173a 0 1794 9 s 16828 I 4381 1 4430 1 4858 15207 15507 1 5775 1 6249 I 667I i1059 ' t 7422 8 1765 1 8092 1 3403 1 470s Sh 4692 % 92 i46 97 I % 92 296 92 396 92 4 % 92 $9697 6%92 196 92 896 92 9 % 92 let - e 0 02050 0 65 % 0 1278 0 7928 0 8520 0 9072 1 0102 1 1078 1 2023 17948 6 3858 - 1 4757 t %47 1 6530 (543 081 h 49160 1201 8 1243 4 12810 1314 6 1345 6 1403 7 1459 4 1514 4 1%94 1624 4 1680 7 1737 2 1794 3 s 0 6928 8 4304 14726 1 5090 1 5399 i % 73 3 6tsa 1 6580 t 6910 1 7335 I 1679 I 8006 8 8318 i ssIF Sh 39 16 8916 139 14 18916 28916 38916 48916 58916 68916 189 16 88916 989 16 798 e. 0 02069 0 6095 0 6616 0 7313 0 7882 0 8409 0 9386 10306 I !!95 1 2063 12916 i 3759 6 4592 1 5419 (510 841 h 500 89 1200 7 12M 9 I276 3 1310 7 1342 5 1401 5 1457 6 1512 9 1568 2 1623 8 1671 8 17M 4 17936 s 4 7022 1 4232 8 4598 I4977 I 5296 1 5577 46065 t 6494 I 6886 I 1252 11598 L 1926 I 8239 1 8538 54 31 79 81 79 131 79 181 19 281 79 381 79 481 79 581 79 681 79 181 79 881 79 981 79 W e 0 02087 0 5690 0 6151 0 6774 07323 0 7828 0 8759 0 9631 1 0470 81289 8 2093 12885 13%9 1 4446 1518 211 h 5c9 81 1199 4 1230 1 1271 1 1306 8 1339 3 1399 1 1455 8 1511 4 1566 9 1622 7 1678 9 1735 7 17929 s 0 Fill I 4163 44472 14869 I 5198 L 5484 3 5980 t 6413 1 6807 1 7115 1 7522 1 1851 8 8164 I 8464 Sh 2476 14 76 124 76 174 16 274 76 314 16 474 76 514 76 474 76 774 76 874 76 974 76 58 e 0 02105 0 5330 0 % 83 0 6296 0 6829 0 7315 0 8205 0 9034 09830 1 0606 IIM6 1 2115 1 2855 1 3588 152k241 h 51840 1896 0 1223 0 1265 9 1302 8 1336 0 13 % 8 1454 0 1510 0 1565 7 1621 4 1678 0 1734 9 8712 J s 07197 1 4096 I 4347 I4763 1 5102 15J96 1 5899 I 6336 I6733 1 1802 1 1450 1 7780 1 8094 I 8395 Sh 18 05 6805 118 05 168 05 26805 368 05 468 05 568 05 668 05 768 05 868 05 968 05 W e O C2123 0 5009 0 5263 05869 0 6388 0 6858 0 77t3 0 8504 0 9267 0 9998 10720 1 1430 1213t 3 2s25 1531 953 h 526 70 11 % 4 1215 5 1260 6 1798 6 1332 7 1394 4 1452 2 1508 5 1%44 1620 6 16771 1734 I i191 4' s 0 7219 I 4032 1 4223 8 4659 L 5010 15311 1 5822 1 6263 i H62 1 1033 L 7382 8 7113 1 8028 I 8329 Sh = Superheat. F h
- enthalpy. Btu per Ib v = Specific v0furne. cu f t per Ib 5 , eritropy. Btu per F per Ib M
( .y. 4
~ .g- Table 3. Superheated Steam-Continued Ats Press.
Lb/$g let $4t $4t lemimatwe -Degrees F4nrenheel
., ($al. temel Water $leam 554 Set 550 FIS 754 800 350 900 1000 1108 12W 1300 1400 150s Sh 11 61 61 61 181 51 t6161 211 61 261 61 311 68 36161 46t 61 561 61 MI 61 761 68 86161 96t s!
. m' W F e 0 02143 04F25 04883 0 5485 0 5993 06449 0 6818 0 7272 0 7656 0 8030 0 8753 0 94 % 1 9142 1 0817 8 1484 1 2143 '
st M h 534 74 !!94 7 1207 6 12 % i 1294 4 1329 3 1361 5 1392 0 1421 5 1454 3 1507 0 1%32 1619 5 1676 2 1733 3 1791 0 s 6 1358 3 3970 I 4098 14557 I 4921 I 5228 1 5500 1.5744 1 5977 I 6193 1 6595 I 6967 I 7317 1 7649 1 1965 1 8267
#f9 Sh 5 42 % 42 105A2 1 % 42 205 42 2 % 42. 305 42 3M 42 4 % 42 SH 42 65542 7% of 8 % 42 9M 42 2SW e 0 02159 0 4460 0 4535 0 5137 0 % 39 0 6000 0 6449 0 6875 4 1245 'O 7603 0 6295 0 8966 0 9622 1 0266 3 0908 8 1529 lb8693 t 542 M 1192 9 1899 3 1249 3 12101 1325 9 1358 1 1389 6 . 1419 4 1448 5 1506 4 1%I9 1618 4 1675 3 4732 5 1790 3 s 0 7434, 8 3910 1.3913 1 4457 1 4833 1 5149 I 5426 156U l 5988 1 6126 1 6530 iHel 11256 8 1509 11985 - 1.8207 Sh 4947 9947 149 47 19947 24947 29947 349 47 44947 54947 64947 14947 04947 94947 IMS e 0 02177 0 4222 0 4821" 0 5312 0 5745 0 6142 0 6515 0 6812 0 1216 0 7881 0 8524 0 9151 09767 1 0373 1 0973 (55453 h % 0 15 till 0 1743 4 1285 7 1322 4 13 % 8 1387 2 1417 3 1446 6 1503 9 1560 7 1637 4 1674 4 1731 8 1789 6 s 0 1507 1 3851 14354 14748 1 5012 1 5354 15408 1 5042 1 6062 1 6469 1 6845 t illF 1 7531 17ks 1 8151 Sh 4372 93 72 143 72 19372 24372 293 72 34372 443 72 543 72 64372 F4312 843 72 943 F2 lie v 0 02195 0 4006 0 4531 05017 0 5440 0 5826 0 6188 0 6533 0 6465 0 7505 0 8121 0 8123 0 1313 0 9894 1 0464 (5123 h H7% llat l 1237 3 1281 2 1318 8 1352 9 1384 7 1415 2 1444 7 1502 4 1H94 1616 3 1473 5 1731 0 1789 0 s 0 7578 1 3794 1 4259 14u4 1 4996 1 5244 1 5542 15719 8.6000 1 6410 I 6787 1 7141 1 7475 17793 1 8097 Sh 3918 8918 13918 18918 23918 289 18 33910 43918 53918 639 18 F3918 83918 939 18 litt e 0 02214 03807 0 4?63 04746 0 5162 0 H38 0 5889 0 6223 0 6544 0 F161 0 7754 0 8332 0 '889 8 9456 1 0007 (561 821 h % 4 78 1187 0 1230 9 1276 6 1315 2 1349 9 1382 2 1413 0 1442 8 1545 9 1%81 1615 2 1672 4 1730 2 1788 3 s 0 1647 8 3738 84160 14582 3 4923 4 5216 I.5478 1.5717 85948 8 6J53 1 6732 11087 1 1422 1 7741 1 8045 Sh 32 81 82 81 132 81 182 8I 232 81 282 8t 332 81 432 81 532 81 432 81 732 81 83281 932 81 18e e 6 02232 0 3424 0 4016 04497 0 4905 0 5273 O MIS ES939 0 6250 0 6045 0 7418 01974 0 8519 0 9055 0 %e4 (567.1 3 h 571 85 1184 8 1224 2 1271 8 1311 5 1346 9 8379 7 1410 8 1440 9 14984 15 % 9 1614 2 1671 6 1729 4 iF876 s 0 1714 1 3643 1 4061 1 4501 1 4851 1 5150 1.5415 1.5658 1.5883 1 6298 I M19 11035 11378 1 7691 1 7996 Sh 22 58 72 58 122 58 172 58 222 58 272 54 322 58 422 54 522 54 622 54 F22 54 822 58 92258 la v 0 02269 0 3299 0 3570 0 4052 0 4451 0 4804 0 5129 0 54J6 0 5129 06281 0 6422 0 7341 8 7047 08M5 0 8836 64423 h 545 58 1180 2 8209 9 1261 9 1303 9 3340 8 1374 6 1406 4 1437 8 1496 3 1%43 1612 0 1660 8 1727 9 1786 3 s E7843 135n 13860 I 4340 I eill I 5022 1 5296 I H44 I 5773 1 6894 16578 1 6937 1 7215 11596 11902 Sh 1293 42 93 11293 14293 212 93 26293 31293 41293 512 93 612 93 71293 81293 912 93 les e 0 02307. 0 3018 0 3176 03M7 0 4059 0 4400 0 4712 0 5084 0 5282 05mt 0 6311 0 6790 0 F272 en37 0 81 %
(581 07) h 598 83 1175 3 11941 1251 4 1296 1 1334 5 1369 3 1402 0 1433 2 14932 IM14 1608 9 1668 0 1726 3 17850 s 0 1966 1 3474 3 3652 3 4181 I 4575 14900 I 5182 1 5436 1.5670 1 6006 I 6444 I 6845 11185 11500 11815
. . . e t
Sh 3 80 5380 103 80 153 80. 203 40 253 40 303 80 40380 503 40 603 to 703 to 803 80 903 P0 1588 e 0 02346 02772 02420 03328 03717 0 4049 0 4350 0 4629 0 4894 0 5394 0 5869 06327 0 6773 0 1210 0 7639
, 1596 205 h 641 68 1170 t it ?6 3 1240 2 1287 9 1328 0 1364 0 13974 1421 2 1490 1 15492 1607 7 16M 2 1724 8 iF83 7
's 0 8085 1 3373 1.3431 1 4022 34443 14782 1 5073 1 5333 l 5572 1 6004 l 63 % 16759 I 7101 I 7425 1 7734
$2 Im e 0 02387 02H5 4513 9513 14513 19513 24513 29513 39515 49513 59513 695 13 795 13 8% l3 h
0 3026 0 3415 0 3748 0 4032 04301 0 45 % 0 5031 0 5482 0 5915 0 6336 0 6 F44 0 7153 4 04 873 624 20 1164 5 1228 3 1279 4 1321 4 1354 5 1392 8 1425 2 1486 9 1546 6 1605 4 IH43 1723 2 17823 s 0 8199 1 3274 1 3861 14312 14667 14%8 1 5235 15478 1 5916 1 6312 1 6678 1 7022 17347 1765F SA 3687 8687 13487 186 87 23687 286 87 386 87 486 87 586 87 686 87 186 87 886 87 IIW e 0 02428 02361 02754 03147 0 3468 0 3751 0 4011 042% 04111 0 5140 O H52 05%l 06348 0 6774 M1313 h 636 45 1158 6 1215 3 1270 5 1314 5 1352 9 1388 I 1421 2 1483 8 1544 0 1603 4 1662 5 1721 7 1 Fat 0 s 0 $309 1 3176 1 3697 1 4183 145H 14867 1 5140 1 5384 1 5833 1 6232 i H01 16947 1 474 I 1585 52 28 98 78 98 128 98 178 98 228 98 278 98 318 98 478 98 578 98 678 98 178 98 87s 98 18E8 e 0 02472 0 2186 O M05 0 2906 0 3223 0 3500 0 3752 03988 0 4426 0406 0 5229 0 % 09 0 5980 0 6343 e62102) # 64849 1152 3 1201 2 1261 1 1307 4 13412 1383 3 1417 1 1480 6 1541 4 1601 2 I%07 in01 1779 7 s 0 8417 1 3079 4 3526 1 4054 1 4444 14768 1 5049 I 5302 L 5153 1 6156 16528 1 6876 l 1204 1 7516 Sh 21 44 FI de 121 44 til 44 221 44 271 44 371 44 471 44 571 44 67144 FTl 44 871 44 im o J 02517 0 2028 0 2274 02647 0 3004 0 3275 0 3571 0 3749 0 4171 04%5 0 4940 0 5303 0 5656 0 600? e628561 # MO16 1145 6 1185 7 1251 3 1300 2 1341 4 1378 4 1812 9 14774 1538 8 1599 t 1658 8 1718 6 17784 s 0 8522 1 2981 1 J 346 1 1925 14338 1 4612 1 4960 1 5219 I 5677 1 6084 1 6458 1 6808 I 7138 1 7451 54 je 14 20 64 20 1I420 164 20 214 20 264 20 364 20 46420 % 4 20 E4 20 764 20 864 20 e 00M65 01883 0 20 % 0 2488 02805 0 3072 0 3312 0 3534 0 3942 0 4320 0 4680 0 5027 05365 0 56 % (635 310 2 47211 l138 3 1168 3 1240 9 1292 6 IJ35 4 1373 5 1408 7 1474 1 1536 2 15 % 9 1657 0 1717 0 17731 s 0 8625, t 2881 1 3154 1 3794 1 4231 1 4578 I 4874 1 5138 I 5603 I 6014 1 6391 16743 1 7075 1 7389 Sh 2te 724 5724 10724 15724 20714 25724 35724 45724 $$724 65724 75724 857 24 e 0 02615 01750 01847 0 2304 0 2624 0 2888 0 3123 0 3339 0 3734 0 4099 04445 04n8 0 5101 0 5418 1642 761 h 683 79 Il30 5 1148 5 1229 8 1284 9 1329 3 1368 4 1404 4 1470 9 1533 6 1594 7 16 % 2 1715 4 In57 s 0 8727 12780 1 2942 1 3661 1 4I25 1 4486 1 4790 1 5060 B M32 1 5948 16327 1 6641 1 7014 1 7330 Sh 8e e 0 0?669 01627 55 5055 10055 150 % 200 M 250 M 350 % 450 55 55055 650 55 75055 850 % 446456 h 0106 0 2134 0 2458 02120 0 2950 0 3161 0 3545 03897 0 4231 04%I 04862 0 5165 695 46 1122 2 1123 9 1218 0 1276 8 1323 1 1363 3 1400 0 18676 1530 9 1592 5 1653 3 17I3 9 11744 s 0 8828 1 2676 1 2696 ! M23 1 4020 14J95 14108 I 4944 I 5463 I 5883 1 6266 I H22 469 % 1 7213 Sh 44 ll 9411 144 !! 19411 244 II 344 II 444 11 544 11 644 11 744 11 844 11 33 e 002n? 01513 01975 02305 02%6 02793 0 2999 0 3372 0 3714 0 4035 0 4344 0 4643 0 4935 162 att h 70718 till2 1205 3 1268 4 1316 7 1358 t 1395 7 1464 2 1528 3 1590 3 1651 5 1712 3 In3I s 0 8929 12%9 1 3381 1 3914 14305 14628 14910 15397 1 5821 16207 16%5 16901 1 7219 Sh = superheat. F h = enthalpy, Stu per Ib v = Specific volume, cu ft per Ib s = entropy, Btu per F per Ib y
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