View source for NUREG-1122, Exam Rept 50-413/OL-88-01 on 880926-29 for Both Units.Exam Results:Four of Five Reactor Operators & Seven of Ten Senior Reactor Operators Passed

{{Adams
| number = ML20245B449
| issue date = 05/06/1989
| title = Exam Rept 50-413/OL-88-01 on 880926-29 for Both Units.Exam Results:Four of Five Reactor Operators & Seven of Ten Senior Reactor Operators Passed
| author name = Brockman K, Moorman J
| author affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| addressee name = 
| addressee affiliation = 
| docket = 05000413, 05000414
| license number = 
| contact person = 
| case reference number = RTR-NUREG-1122
| document report number = 50-413-OL-88-01, 50-413-OL-88-1, NUDOCS 8904260115
| package number = ML20245B444
| document type = EXAMINATION REPORT, TEXT-INSPECTION &amp; AUDIT &amp; I&amp;E CIRCULARS
| page count = 200
}}

=Text=
{{#Wiki_filter:_                                 _.
[.
                  . j#"'*%$
3'                              '
                                                                     <                        UNITED STATES                                                                                                                                          1
                                                  , ,                   ' NUCLEAR REGULATORY COMMISSION
                                                   '*                                                          REGION 11
                 ' o\ e....                      j[                                   101 MARIETTA ST N.W.
I ATLANTA. GEORGIA 30323 ENCLOSURE 1 EXAMINATION REPORT 413/0L-88-01 L                Facility Licensee:                                           Duke Power Company                                                                                                                                                   I 422 South Church Street                                                                                                                                                l Charlotte, NC .28242 1
                  . Facility Name:                                              Catawba Nuclear Station i
Facility Docket No.                                          50-413 and 50-414 Written examinations and operating tests'were administered at the Catawba Nuclear                                                                                                                                                  ;
Station near~ Clover, South Carolina.                                                                                                                                                                                              ;
Chief Examiner f -N(O N.                                      NiTh47                                                                                                              4-9-89 Dated Signed J nes H. Poorman, III Approved by:                                      td             ut'                         W                                                                                   e/ 89                                      !
t Kphneth E. P ocpran, Chief                                                                                                        T) ate Signed Operator Licensing Section 2 i
I Summary:
Examinations on September 26 - 29, 1988.                                                                                                                                                                                            ;
Written examination and operating' tests were administered to 15 candidates,11 of whom passed.
Based on the results described above, 4 of 5 R0s passed and 7 of 10 SR0s j-                 passed.
l f.
8904260115 890407 .
PDR         ADOCK 05000413 V                                             PNU;
           +-_.2          .-.,,.-,c..a.-.a_-._:.           _w.-- . . _ . . .      _    u._-um--.-__,,a.---_.--           _ . _ _ . _ - _ - . . _ _ _ . - .             .___m._-_e___m_____                        .____m,_,__,____.____---m_-_m_
J l
4 REPORT DETAILS
: 1. Facility Employees Contacted:
                               *H. Barron, Superintendent of Operations                                                              .
                               *W. Barron, Director of Operator Training                                                           I
                               *M. Brady, Assistant Operating Engineer
                               *J. Cox, Manager - Catawba Training R. Mayes, Ir,structor
                               *C. Kiker,- Instructor
                               *G. Spurlin, Senior Instructor
                               *D. Tower, Operating Engineer
* Attended Exit Meeting
: 2. Examiners:
                               *J. Moorman, III, Region II T. Guilfoil, Sonalysts, Inc.
M. Morgan, Region II C. Rapp, Region II G. Salyers, Region II F. Victor, Sonalysts, Inc.
G. Weale, Sonalysts, Inc.
* Chief Examiner
: 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided Glen Spurlin with a copy of the written examination and answer key for review. The NRC Resolutions to facility comments are listed below.
The following remarks address the facility's generic comments. These comments can be found in Enclosure 3 of this report.
: 1. The exam administered on September 26 was a Replacement Examination and not a "Requal Exam". The intent and expectations of the two exams are different.
The NRC is required to ensure that operators are minimally competent for the job of operating a nuclear power plant. This is done, in part, by covering the topics listed in 10 CFR 55.41 and 10 CFR 55.43 on a written examination. The importance of subjects in these topic areas is determined partly from the facility's learning objectives and partly from NUREG 1122, "Knowledges and Abilities Catalog for Nuclear Power Plant Operators."

2
                                   -It is the utilities' function to train the candidates, at a minimum, to both the examination standards established by 10 CFR 55 and to those needs identified by the plant specific job and task analysis.
The NRC will not limit its examination solely to the standards established by the utility.        The NRC is confident that the facility shares the goal of the NRC in assuring that once candidates receive a license to operate the plant, they will be safe and competent operators.
: 2. All questions were tied to objectives if a fair extrapolation of the objective is applied.       If no objective existed, an importance rating from NUREG 1122 was provided.
: 3. The only system information supplied from Catawba for generating the exam was " Training Handouts".       The facility was reluctant to release any more thorough or detailed information, ie. System Descriptions.
System Descriptions were requested by the NRC. The NRC was told by Catawba Training Management that the System Descriptions were not up to date, contained errcrs and were not used often. When requested by the NRC examiners, the person contacted said there were many volumes of System Descriptions and " selected ones" would be sent.
The exam was not constructed of isolated training trivia, as is suggested. Both a member of the plant training staff and the plant operations staff reviewed the exam prior to its administration.
Except for a few specific exceptions, they made no comments on the final products relevancy or clarity.         This, in effect, further established the content validity of the exam items.
: a. R0 Exam Coment Resolutions (1) Question 1.03 NRC Resolution:    Comment not accepted. Supporting documentation provided by the facility substantiates that reactor fission power decreases to less than 1% in 30 seconds. The distractors are of enough diversity to support an appreciation of power decrease, not specific value memorization.
(2) Question 1.10 NRC Resolution:     Comment accepted. The answer key has been changed as recommended by the facility.
(3) Question 2.04 NRC Resolution:     Coment accepted. The answer key has been changed as recommended by the facility.
_ _ - - - - - - - - - - - _                                                                                     1

3 (4) Question 2.05 NRC Resolution:       Comment partially accepted. The setpoint of 730 gpm is changed to 780 gpm based on updated material                                                                     !
(0P-CN-H0-CA, Rev 02/03-08-88/TJC), which was not provided for exam preparation.
l Operating with the CAPT discharge valves to A and D S/G's closed is not a design feature.         No change to the answer key will be made.
(5) Question 2.08 NRC Resolution:        Comment accepted. The answer key has been changed as recommended by the facility.
(6) Question 2.11 1
nRC Resolution:      Comment accepted. The original-answer was taken from an outdated reference provided by the facility for exam preparation. The answer key has been changed to accept low level or low-low level .
(7) Question 2.13 NRC Resolution:       Comment not accepted.      Operators should be aware that valves located below the flood plane are " frozen" in position during a flooding casualty. Information on this item was taken from Catawba System Description CNSD-0142-01, pp.6,7.
If the valve nomenclature is wrong, the facility should revise the system description.
(8) Question 2.14 NRC Resolution: This question addressed an existing capability which, if actuated, would affect the operators' indication and operation of the steam dumps. The question is relevant and pertinent to the operators job. No change to the answer key will be made.
l (9) Question 3.06 NRC Resolution:       Comment accepted. The answer key has been changed as recommended by the facility.
(10) Question 3.08 NRC Resolution: Comment partially accepted. The full load d/p of 200 psi has been changed to 215 as stated in the current                                                                j reference. In part 'C',       any answer stating no response, based on a stated assumption associated with the 120 second lag circuit, will receive full credit.
f i

I i
4'                                       l i
l (11) Question 3.09 NRC Resolution:                   Coment accepted. The answer in part 'b' has been changed to read "two (i) loop loss of flow".                                                !
1 i
(12) Question 3.10 i
NRC Resolution:              Coment accepted.                 The answer has been changed           l to "If. load is greater than 80% (.25) and one CFPT trips, (.25)                                    1 a runback will occur until load is less than 80% for 30 seconds
(.25) or load is less than 70% (.25).
(13) Question 3.13 NRC Resolution:                  Comment acknowledged.             The facility provided
: answer is equivalent to the answer key.                               For additional clarity, the answer to part 'a' and 'c' have been reworded as recommended by the facility.
(14) Question-4.13 NRC Resolution:                Comment not accepted.               The additional answers provided by the facility are not consistent with the conditions stated in the question. No change to the answer. key.
(15) Question 4.14 NRC . Resolu tion:         Comment accepted.                  The answer key has been changed to allow the equivalent answer provided by the facility.
(16) Question 4.16 NRC Resolution:             Comment partially accepted.
Part A - Alternate answers 1 and 2 provided by the facility will be accepted for full credit, provided the candidate state , that the valve is being set or reset to the prescribed throttle position.
Part B - This is not accepted; however, credit will not be deducted for including this in the answer.
Part C - The additional answer provided by the facility will be accepted for credit.
(17) Question 4.17 NRC Resolution:                        Comment accepted.        The answer key has been changed to accept the facility recommended response.                                           The facility should update it's training material to reflect this information.
L____________

5 (18) Qutstion 4.18 NRC Resolution:    Comment accepted. The definition provided by the facility is acceptable as an alternative answer.                         The facility should update it's training material to reflect this information,
: b. SR0 Exam Coment Resolutions (1) Question 5.07 NRC Resolution:   Comment not accepted. As stated in the facility comment, TRUE is the correct answer. No change to the answer key.
(2) Question 5.19 NRC Resolution:    Comment acknowledged.         Errors or assumptions made in the calculation will be carried forward for grading purposes. No change to the answer key.
(3) Question 6.05 NRC Resolution:   Comment accepted. The question has been deleted.
(4) Question 6.06 NRC Resolution: Comment not accepted. The question deals with an operational aspect of equipment which is operated by licensed operators. NUREG 1122, Knowledges and Abilities Catalog, rates "The ability to monitor automatic operation of the ac distribu-tion system, including operation of inverter (synchronizing light)" as 2.7/2.9. (062000A3.04). No change to the answer key will be made.
(5) Question 6.07 NRC Resolution:    Comment accepted. At the pre-exam review, the facility requested the answer be changed to that stated on the exam answer key.
The answer key would have been changed to read all valves open except CA58A which would be closed, as per reference OP-CN-H0-CA page 17 of 26 sec. 3.d (Rev. 01/04-15-87/WSR).
The Training Department stated in a phone conversation on October 7, that the information in the handout was wrong and that supporting documentation, ie. E prints, would be forwarded.
Based upon this additional information, the answer will be changed to all valves open.

6 (6) Question 6.09 NRC Resolution: . Comment not accepted. The question only asks for power. No credit will be given for describing SUR response.
No change to the answer key.
(7) Question 6.10a NRC Resolution:      Comment not accepted. There is an-error in the Facility response concerning the dispersion of information to the candidates. The exam was interrupted to get everyone's attention, and question 6.10 was addressed, stating that it meant any dump that would or could receive a signal, and that the valve did not necessarily open.
If the B Reactor Trip Breaker did not open, the SR0 should be aware that the B Rx Trip Breaker controlled contacts to determine whether the Trip Controller or the Load Rejection Controller was controlling. Additionally, Question 6.10a was not questioned in the pre-eview. No change to the exam or answer key will be made.
(8) Question 6.10c NRC Resolution: Comment partially accepted. The answer will be changed to accept 5.8 +/- 2 degrees F. Although the information solicited by the question may come from a graph, a knowledgeable operator would know the response of the steam dump system to various plant conditions.       This question is supported by NUREG 1122, 041020K105 (3.5/3.6) 041020K412 (3.7/3.9).
(9) Question 6.11 NRC Resolution: Comment not accepted. The question deals with the design of the rod control system and is supported by NUREG 1122, 001000K4.04 (3.5/3.8). No change to the answer key will be made.
Operators should understand the basic operating characteristics of the Rod Control System. This includes the functions of the major components. Irrelevant of whether the topics are addressed in the facility's learning objectives, the safety significance, as supported by the K/A Catalog, supports their continued inclusion on future written and operating exams.
The applicability of this question to CNS operators was specifi-cally addressed at the pre-exam review and comments were not made at that time.

7 (10) Question 6.13 NRC Resolution:      Comment accepted. The answer key will be modified to not require the specific names of the gain units, but instead, a concentration on their operating characteristics.
Also, the question value was corrected to 1.5 points.
(11) Question 6.16 NRC Resolution:     Comment acknowledged. No change to the answer key was required.
(12) Question 6.18 NRC Resolution:     Comment accepted. However, the point values were adjusted tr maintain part (a) at 0.5 points and part (b) at 0.5 points.
(13) Question 6.20 NRC Resolution: Comment acknowledged. As on past exams, informa-tion enclosed in parenthesis is not required for credit and no points are deducted if the information is not included in the candidates answer.
(14) Question 7.05 NRC Resolution:     Comment accepted. The question will be deleted.
(15) Question 7.09 NRC Resolution: Comment not accepted.      This is general knowledge required in General Employee Training. Also, element 8 of Employee Training and Qualification System (ETQS) Training and Qualification Guide C0-S0010 requires the Senior Operator to have this knowledge. Additionally, 10 CFR 55.43(b)(4) requires that                          j the Senior Operator be familiar with contamination conditions.                          I No change to the answer key will be made.                                               l (16) Question 7.13 NRC Resolution:      Comment not accepted. However, answers that                       {
demonstrate a familiarity with the RP immediate actions will receive full credit. The questions' intent is to ascertain familiarity, not procedural memorization.
i (17) Question 7.14a                                                                          j i
NP,C Resolution:     Comment accepted. The answer key has been                         I cha.iged and the points redistributed.                                                  l
__ _ _____ _                                                                                              J

                                                                                                                               . _ _ = _ _ _ _ _ _      __ _ _ _ _
i 8
I (18) Question 7.14b NRC Resolution: Comment not accepted. Items required by the question are the most basic of operator actions. Items IC, 20 and 3C of ETQS C0-R0116 require this knowledge of all licensed operators.
(19) Question 7.15 Comment partially accepted. The question did NRC Resolution:
not contain information on, nor imply an ongoing security event.
However, if candidates stated this as an assumption, ALERT will be accepted for full credit.
(20) Question 8.01 NRC Resolution:     Comment not accepted. Information in Table 3.3-1 applicable to the question was not changed by Amendments 48 and 41. Sufficient information was provided in the question to arrive at the answer. Amendments 48 and 41 were not included in the Technical Specifications sent with the training material provided for exam development, nor were they provided to the examiners at the exam review. No change to the answer key will be made.
(21) Question 8.02 NRC Resolution:     Conment not accepted. Discussions with the proctor and review of the proctors notes indicate that the correct guidance was given to the candidate.       Additionally, based on the candidates answer, the comment is moot.               No change to the answer key will be made.
(22) Question 8.19 NRC Resolution:    Comment accepted. The answer will be changed to state "5 or no maximum number". The  information from Station Directive 4.2.1 used to support this comment was not provided to the NRC for exam preparation, nor was it mentioned at the exam review.
(23) Question 8.24 NRC Resolution:    Comment accepted. The answer will be changed to "no action required".
: 4.                    Pre-Exam Review On September 19-21, 1988, NRC examiners involved in the administration of the Operator Licensing Examination met with representatives of the Catawba Nuclear Station Training and Operations staff to review the upcoming written and operating examinations. All facility reprevntatives having

i 9                                                                               .
i prior knowledge of the examination were required to sign pre- and post-                                               )
exam security agreements to ensure exam integrity. This review was conducted in an attempt to improve the quality of the examination and to reduce the number of post-exam comments generated as a result of                                                    <
                                         . imprecise communication of the test items.
The goal of providing clearly worded questions to the candidates was for                                             j the most part, met. However, post-exam comments made by the training staff indicated that a more thorough review by the facility would have been                                       i beneficial. Many of the comments were necessitated by incorrect informa-                                             l tion in the training materials, improper interpretation of plant specific information, and additional (sometimes conflicting) guidance promulgated in materials not presented to the NRC for exam preparation. The " cost efficiency" in conducting a pre-exam review where so many deficiencies                                              j were not identified was questioned.
On March 28, 1989, a meeting between the NRC and Catawba management was                                             l held at the Region II Office to discuss the continuation of the                                                     )
pre-examination review process at the Catawba Nuclear Station.                                            The facility expressed their desire to continue this initiative at the Catawba Nuclear Station. The facility stated that they would provide a                                         '
team dedicated to the pre-examination review in order to obtain a better examination. It was agreed that specific guidance concerning how pre-exam reviews should be conducted was needed. Based on the facility's presenta-                                         '
tion, it has been decided that the pre-review process will continue at' Catawba.
: 5.                       Exit Meeting At the conclusion of the site visit the examiners met with represent-atives of the plant staff to discuss the results of the examination.
There were no generic weaknesses noted during the oral examination.
The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was al o noted and appreciated.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
L______m.__.__.___ _ . _    . _ _ . . _ _ _ _ _ _

s              .
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:                             _gGIAWpA_1&2_____________
REACTOR TYPE:                         _PWB-WEg4________________
DATE ADMINISTERED _@@f92f_26________________
EXAMINER:                             _BEGIgN_11_______________
7)ne-          ^
CANDIDATE:                            __j_ A y_ y__U_F- ____________
INEIBUgIlgNS_IQ_CGNp196Ig1 Use separate                             paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer                                                             sheets.        Points for each question are indicated in parentheses after the question.                                                                   The passing grade requires at least 70% in each category and a final grade of at least 80%.                            Examination papers will be picked                                  up si:: (6)        hours after the examination starts.
                                                                            % OF CATEGORY                           % OF       CANDIDATE'S            CATEGORY
__YBLUE_ _IQIGL                               ___SgQBE___            _y@LUE__ ______________gGIEGQBy_____________
26, 09
_29s99__ 239r@t-                              ___________            ________
: 1.      PRINCIPLES OF NUCLEAR POWER PLANl UPLRATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 4
_22199__ _22t2@                               ___________            ________ 2.         PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS g                              2.1 a B
_21159__ z@@r43                               ___________            ________ 3.          INSTRUMENTS AND CONTROLS u<
_22mgQ__ _-2Q ds                              ___________            ________ 4.         PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL I
11# 99__                                      ___________            ________%           Totals Final Grade All work done on this examination is my own.                                                             I have neither given nor received aid.                                                                                                                                                                          ]
Candidate's Signature l
l l
I

fli__EBING1ELES_QE_NQQLEGB_EQWEB_E68NI_QEEB811QNs                                                                                                                  PAGE 2-THERMODYNAMICS                                                                                                       S _UE81_IB8NSEEB_8ND_ELUID_ELOW 4:           .
b                                                                                                                                                                                 >
1 JOUESTION                                                 1.01                                                                         (1.00)                              l
           . MULTIPLE CHOICE:
Which_ONE of the following.is NOT compensated for by excess reactivity?
: a.                                   Fuel burn up,
: b.                                   Fission product poison buildup.
                       .c.                             -Chemical r*- m..
                       -d.                                    Reactivity effects of fuel and moderator temperature.
     . ANSWER                                                  1.01                                                                          (1.00)
C..
REFERENCE-CATAWBA Handout                                                                                                          OP-CN-HO-RP-p.6-WESTINGHOUSE,. Reactor Core Control for Large Pressurized Water Reactors, 1983, . p'. 2. 7
           .192OO2K109                                                                                                ....(KA'S).
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

riz__EBINGIELES_9E_UUGLE88_EgWEB_E68NI_gEEB8'IlgN i                                                                                                                                                                                                      'PAGE-   3 THERMODYNAMICS _Hg8I_IB8NSEgB_8Np_ELgig_E6QW
                  . QUESTION       1 ~. 02                     (2.00)
MULTIPLE CHOICE:
: 1. . Which of the f ollowing reactivity changes is NOT a contributor to total
                           . power defect when core power output is increased from 50 to 100 percent
                          - at. the beginning of core lif e (BOL)?_                                                                                                                                                                                                           (1.0)
: a.       Control ~ rod position change
: b.      Moderator temperature change
: c.       Moderator voids percentage change
: d.       Fuel temperature l change
: 2.       Which ONE of the following factors is the predominant effect on making the fuel Doppler coefficient less negative at EDL?                                                                                                                                                                                              (1.0)
: a.      The buildup of gases in the' fuel' rod gap.
: b.       Fuel- densification
: c.       Clad creep d..      Plutonium 240 buildup ANSWER          1.02                        (2.00)
: 1. a.
: 2. c.
REFERENCE CATAWBA Handout CN-OP-HO-RCO p.16 and 18 WESTINGHOUSE, Reactor Core Control for Large PWRs, 1983,                                                                                                                                                                                     p. 3-39.
192OO4K107                   192OO4K108                                                          ...(KA'S)
(*****              CATEGORY 01 CONTINUED ON NEXT PAGE *****)
-_. _ _ - - _ - _       __m._    _     ___   _________m__.___m    , _ , _ _ _ , _ , , _ . _ _ , , _ _ _ _ _ _ , , _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ , _ _ _ _ _ , , , , , _ __ _ _ _ , _ , _ _ , , ,

Tig__EB1NCIPLES:OF NUgLg6B;EgWEB_EL8NT_gPgB8 TIONm                                                                        PAGE-    4
      . -IdEBd99YN0dlGEm_HE61_lB8N@EEB_GNQ_ELUID_ELgW-
: QUESTION. '1. 03 -                (2.00)
MULTIPLE CHOICE:
     'A reactor is initially operating at 100 percent-power when a reactor trip occurs.
1.'    Approximately.how long after the trip will it take for reactor fission power to decrease.to less than'1 percent power?                                                            (1.0)
: a. 1 second
: b. 30 seconds,
: c. 60. seconds
: d. 90 seconds
: 2.    'If the rate'of decrease of the reactor fission power stabilizes at 0.01% 4 minutes after the trip,-how many additional minutes will-be required for. fission power to~ decrease to 0.OOO1 percent?
            - ( 1 '. 0 )
a-   3 b.. 4
: c. 5
: d. 6 fANSWER               1.03          (2.00)
: 1. b.
: 2. d.
REFERENCE CATAWBA Handout OP-CN-HO-RK p.            23,24 WESTINGHOUSE, Fundamentals of Nuclear Reactor Physics, 1983,                                           p. 7-10.                   j
                                                                                                                                            )
192OO8K123-                2.9           ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
                                                                   - _ - _ _ _ _ - _ _ - _               _          ____ - _            a

pc.                   .    .
cit __EBING1ELES OF NUCLEAR POWER' PLANT OPERATIONm                                                                                                                               FAGE     5-
:TBEBdQQyg8diggy_BE@I_IB8dgEEB_8ND_E6g1D_E(gW w
QUESTION         .1.04                                            (2.00)
          .IMUdTIPLE CHOICE:
: 1. Which ONE of the f ollowing descriptions best supports the ree son .why Xenon reactivity increases. sharply'after a trip following one thousand (1000) hrs. at 100% power?                                            (1.0)
: a.           Xenon decays'less rapidly due to a' reduction.in tht' ' neutron flux.
: b.           Iodine half-life is much shorter than Xenon half-life.
c..          Iodine and Xenon. production'is greatly ~ increased due to
                                           .the reduction in neutron flux.
: d.          'Due'to reduced neutron absorption, Iodine concentration increases, and Xenon decays-directly from Iodine, thus. Xenon
                                           . increases.
l2. Which ONE of the following statements concerning fission product poisoning ef f ects -is correct?                                                                                                                                        (1.0)
: a.           Xenon is produced directly from fission and neutron
                                           . absorption but Samarium' is produced f rom fission only
: b.           Xenon is removed by. decay and neutron absorption but Samarium is removed by-neutron absorption only
: c.           Equilibrium ~ xenon is independent of power lovel but equilibrium Samarium is dependent on power level
: d.           Xenon equilibrium is reached in about 40 hours following a large load increase but samarium equilibrium is reached in about 200 hours following a large load increase.
           . ANSWER           1.04                                            (2.00)
: 1. b.
2.. b.
REFERENCE L
CATAWBA Handout OP-CN-HO-RP p.8 through 12 WESTINGHOUSE,' Reactor. Core Control for Large Pressurized Water Reactors, 1983, pages 4-11 through 4-33.
192OO6K103                    192OO6K104                                 192OO6K106                                                ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
a-___---_--_--_______                         - _ - _ - _ _ _ _ - _ _ _ _ _ _               _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _ ,                       _    _ _ - - -                             .1

Iz__EBIN91ELES_9E_N996EGB_EgWEB_EL@NI_gEEBGIlgNi                                    PAGE   6 THERMODYNAMICS _ HEST _IBGN@EEB_GUD_EL91D_EL9W n
  -QUESTION    '1.05         (2.00)
MULTIPLE CHOICE:'
: 1. . .The moderator. temperature coefficient'(MTC) becomes LEAST NEGATIVE (the absolute value'becomes smallest) under which one of the f ollowing conditions?                                                                      (1.0)
: a. Average temperature in decreased while boron concentration is increased.
: b. Average temperature is decreased while boron concentration is decreased.
: c. Average temperature is increased while boron concentration is.
                     ' increased.
: d. Average temperature is increased while boron concentration is decreased.
: 2. Select l the PRIMARY reason why the moderator temperature coef ficient becomes more. negative from BOL to EOL7-                                         (1.0)
: a. Decreased fuel temperature at EOL.
: b. Decreased baron concentration at EOL.
: c.  . Decreased Beta-effective (delayed neutron fraction) at EOL.
: d. Increased flux hardening at EOL.
ANSWER      1.05         (2.00)
: 1. a.
     .2. b.
REFERENCE CATAWBA Handout CN-OP-HO-RCO p. 11 and 12 WESTINGHOUSE, Reactor Core Control for Large PWRs, 1983 p.3-20 to 3-28 192OO4K103       192OO4K106      ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

    ,,~1i__EBINCIPLES_QE_Ugg6E8B_EQWEB_EL8dI_QEEBATIQNm                                                               PAGE  7
                        -THERMOQYN8 mig @t_HEBI_IBONSEEB_GUD_ELUID_EL9W QUESTION                      1.06        (2. 00).
MULTIPLE CHOICE:
Aireactor has been' shut'down-from 100 percent power with all control rods fully inserted and cooled down to 140 degrees F over 3 days. During the cooldown, baron ' concentration was increased by 100 ppm. Given the-.                                           .
f ollowing absolute values of reactivity change f rom 100% power to 140 degrees F. 3 days later Xenon          = 2575 pcm Rods           = 6938 pcm Temperature    =   $50 pcm Doron          = 1140 pcm Power Defect = 1525 pcm
: 1.                  . What'was the. shutdown margin at 100% power?                                          (1.0)
: a.   - 5413 pcm-
: b.   - 5963 pcm
: c.   - 6938 pcm
: d.   - 7913 pcm
: 2.                 .W hat-is the shutdown margin at 140 degrees F. after 3 days?                              (1.0)
: a. 3428 pcm
: b.   - 4863 pcm
: c.   - 6478 pcm                                                                                j i
: d.   - 9053 pcm ANSWER                        1.06         (2.00)
: 1.                 a.
: 2.                  a.
REFERENCE CATAWBA Handout OP-CN-RB-HD p.5 and OP-CN-HO-RP p.12 192OO2K113                        192OO2K114     ...(KA'S) i
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

lh__PBINCIPLES=OF_dUCLEAR POWER _PLONT_gPgB8I19N1                                                           PAGE= 8 IU4Bd99XU8d1GSt_UEBI_IB8BEEEB_@ND_E691p_ELQW
      =OUESTION' 1.07                                                 (1.00) 1.
        ; MULTIPLE CHOICE:
        .With rod' control in-manual.and the plant stable at 70 percent power (Tave =-
' '        Tref), the.RCS baron concentration;is REDUCED by two (2) ppm. No other operator action is taken.and generator load remains constant. Which ONE of:
the f ollowing best describes the plant response?
: a.             Reactor power-stabilizes above 70 percent and Tave stabilizes at
                                                     ' Tref.
: b.             Reactor power stabilizes at 70 percent and Tavo stabilizes above Tref.
: c.             Reactor power stabilizes at 70 percent and Tave stabili:es at Tref.
: d.             Reacter power stabilizes.above 70 percent and Tave stabilizes above; Tref.
ANSWER                                         1.07            ( 1. 00 )
H            b.
        -REFERENCE CATAWBA Handout OP-CN-HD-RP p.7
        . WESTINGHOUSE, Reactor Core Control for Large PWRs, 1983,                                      p. 9-18.
192008K120                                         ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)                    l l
i

cl __EBINCIELES_gE_NUGLEGB_EgWEB_E68NI_QEEBBI1Qdt                                                                         PAGE     9
    ,'       . THERMODYNAMICS t HEAT TRANSFER $ND_ELUID FLOW
                                                                                                                                        \-
l QUESTION           1.08'           (2.00)                                                                                                l MULTIPLE CHOICE:                                                                                                                      i i
zi..       Two. identical reacto.         are taken critical usino continuous rod-                                                    1 withdrawal.         Reactor A has a rod speed of 48 '..eps per minute and                                                    l Reactor D has a rod speed of. 24 steps per minute. When the reactors.                                                        I reach criticality, which DNE of the following statements.is correct.                                                         J (1.0) a.--Reactor A will have a higher source range counts than Reactor B.
I
: b. BothLreactors will have the same source range counts.
: c. Reactor D will have a critical rod height greater than Reactor A.
: d. Both reactors'will'have the same critical rod height.
: 2.       A reactor is exactly critical at 1000 CPS in the source range.                                                If a neutron. source'is added, which ONE of the!f ollowing correctly describes
                .the response of source range count rate.
(1,0) 1
: a. Increase exponentially with time.                                                                                     I
: b. Increase linearly with time.                                                                                          I
: c. Romain constant at 1000 CPS.
: d. Decrease exponentially with time.
L.
ANSWER             1.08             '2.00)
(
: 1.      d.                                                                                                                           !
:2.      b.                                                                                                                           i 1
REFERENCE j
    ~ CATAWBA Handout OP/CN-HO-SCM p.4 and p.18 I
192OO8K102                172OO8K104                                       ...(KA'S)
I i
i l
1
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
i l                                                                                                                                             l t-                                                                                                                                           1
                   -          -      -         - _ - _ . _ _ - _ - _ - _ _ _ _ _ - . _ _ _ _ _ - _ _ _ ______-__._ - __ _ -     ___ __D

Ja c PRINCIPLES'OF NUCLEAR' POWER PLANT OPERATION t                                                          PAGE    10 THERMODYNAMICS      t _HESI_IBONSEEB_8ND_E6Ulp_E60W o.
L QUESTION-;1.09                                               -( 2. 00 ) -
i..
LMULTIPLE' CHOICE:
L.                         1 :..                        When the rods:are operated in automatic rod control, which onelof the following plant. temperatures remains essentially constant as reactor
                                                        . power is increased from.15 percent to 75' percent?              (1.0)
: a. T-steam b,   T-average
: c. T-reference
: d. T-cold ~
: 2.                             Which one~of the following UNIT 2 steam generator parameters remains directly proportional to: reactor power as turbine power is ramped from 25 percent to 75-percent rated power with rod control in aut'omatic7 (1.0) a.-  Steam flow
: b. Steam pressure
                                                          'c. Steam generator: level o
: d. Delta-H (steam enthalpy minus feed enthalpy)
          -ANSWER                                               1.09          (2.00)
: 1. , d .
: 2.                       .a.
CATAWBA LP                                OP-CN-HO-SLC p.13
                    ; WESTINGHOUSE, Reactor Core Control for Large PWRs, 1983, p.3-33.
CATAWBA LP OP-CN-HO-SLC p.12 through 18 & OP-CN-HO-IFE p.7 l
WESTINGHOUSE, Thermal-Hydraulic Principles and PWR Applications, 1982,                              p.
12-11,                              12-13.
REFERENCE
:192OOBK121                                         ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

   .t.                              . . . .                 .
L fli;_EBINCIPLES OF NUCLEAR POWER PLANI _QEERATIONg                                                                                                                                                                                  PAGE          11 ISEBd9DYN801GEi_HE81_IB8NSEgB_8ND_ELUID_EL9W
['
     ' QUESTION                                         1.10        (1.00)
EMULTIPLE CHOICE:
       'As. coolant temperature increases, differential boron' worth becomes:
Less negative because'less baron must be added to cause an equal'
                                             .a.
                                                       , increase in boron concentration,
: b. Less negative because the core contains less boron than at lower temperatures.
c.. More' negative because.the density of the boron solution in;the moderator decreases faster.
: d. Mor. 7 negative because more baron is expelled from th                                                                                                                 are f or an equal increase in moderator temperature.
 >IANSWER                                               1.10        (1.00) b . ' gy,
       ' REFERENCE 1 CATAWBA Handout OP-CN-HO-RP p.7 WESTINGHOUSE, Reactor Core Control for Large PWRs, 1983,                                                                                                                                                    p. 5-14.
192OO4K110                                           ...(KA'S)
    . QUESTION                                          1.11        (1.00)
MULTIPLE CHOICE:
       .During a reactor startup, control rods are withdrawn such that 1,000 pcm
        -(1% delta-K/K) of reactivity is added.                                                                                                                                   Before the withdrawal Keff was 0.97
       .and stable count rate was 500 cps.                                                                                                                         What will the approximate final steady state count rate be following rod withdrawal?
: a. 750 cps.
: b. 1000 cps,
: c.  '2000 cps.
: d. 2250 cps.

Lit __EBING1ELES_QEiNWRLEGB_EQWEB_ELGNI_9EEBBIl0Nt.                                                                                                                                                        PAGE ,1:2 IUEBdQDYUGu1GSu- HEAT- TRANSFER AND_ELUID_ELOW ANSWER                                              1.11            (1.00)
         .a.
REFERENCE JCATAWBA Handout'CN-OP-HO-RCO p.8-through-12
: WESTINGHOUSE, Reactor Core. Control for Large Pressurized Water Reactort,-
is      1983, p. 9-10.
       .192OOBK104                                               ...(KA'S) 1.
DOESTION                                            1.12'           (2.00)
MULTIPLE-CHOICE:
1..How does/the convective heat transfer coefficient vary as reactor
                  . coolant flows up along a fuel rod which experiences departure from
: nucleate boiling (DNB) near the top of the fuel rod?-(SELECT.THE CORRECT ANSWER)-                                                                                                                                                                                      (1.0)
                               -a.                        Increases continuously
                            ~ b.                          Decreases continuously
: c.                     Increases,:- then . decreases
                                                                              ~
: d.                     Decreases,:then increases
: 2.                Which of the f ollowing reactor coolant system (RCS) parameters has the LEAST effect on the departure from nucleate boiling ratio (DNBR)?
Consider each separately.
: a.                     Coolant baron concentration.
: b.                      Local power density.
: c.                      Coolant flow rate,
: d.                      Cold leg temperature.
1
__--.-_-__--------__--.__--___x                       --~__-_-_.-___.--_-__a--.__-----a--                   - - . - - . . ~ . - . - - . - . . _ . _ - - - - - - . - - +
                                                                                                                                                                                                                    - - _ - - _        _- - ~ . - .

it__EB1891ELES_9E_NQQLEGB_EQWEB_EL8NI_QEEBGIlgNo                                                               PAGE- 13 THERMODYNAMiggt_Hg8T_TB@NSEEB_8NQ_FLyIQ_ELgW ANSWER.                                               l1.12-          (2.00)
: 1. c.-
: 2. : a.                                      '
s     REFERENCE
     -CATAWBA Handout.OP-CN-HO-HT p.10 and: 11; OP-CN-CTH-CTH p.13                       '
WESTINGHOUSE, Thermal-Hydraulic Principles and Applications to the PWR,-
     !Vol.'2,J1982,                                                 p. 13-24 and Vol.1, 1982,             p. 3-78 192OO8K102                                                  193OO8K105             ...(KA'S)
   . OUESTION' 1.13                                                      (1.00)
IWhich'ONE of the following effects will occur as a result of increased f ouling of - main condenser tube bundles? (Assume cooling water flow:and steam flow rates remain constant)
: a. Cooling water outlet temperature will decrease
: b. Condenser hotwell temperature will decrease c..   . Condensate depression will increase:
: d. Condenser Heat rejection will increase ANSWER                                                 1.13           (1.00) a.
REFERENCE
     . CATAWBA' Handout OP-CN-HO-HT p.12 WESTINGHOUSE, Thermal-Hydraulic Principles and Applications to the Pressurized Water Reactor, 1982, p.9-19 191006K112                                                   ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
        - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                         -    _ _ . _ _        . _ - _                   i

ilt__EBINCIPLES OF'NUCLEAB_EgWEB_ELONI_gEERAllgN1                                               PAGE. 14' LIUEBd9DYN8dicSx_dEBI_IBBNSEEB_GND_E6Ulp_ELgW i
EQUESTIONz 1.14                                 (1.00).
1 MULTIPLE CHOICE:
     ;Which of the' f ollowing illustrates . radiation heat transf er?
: a. Heat. transfer from a. fuel pellet'to the fuel cladding.
: b. Heat-transfer from the? fuel' cladding to'a steam generator,
: c. . Heat' transfer from the fuel cladding to the reactor coolant via subcooled nucleate boiling, dl . Heat transfer from the fuel cladding to the core barrel within a voided reactor vessel.
ANSWER                        1.14             (1.00)
        .g REFERENCE
    -CATAWBA Handout OP-CN-HO-HT p.9 WESTINGHOUSE, Thermal-Hydraulic Princ'iples and Applications to the PWR,
      .Vol .- 1, 1982, p. 3        193OO8K101                           ...(KA'S)
  ' QUESTION                     1.15             (1.00)
     ' MULTIPLE' CHOICE:
Which ONE of the following operations is likely to cause water hammer in a fluid system.                        (Consider each operation separately).
: a. Starting a pump with the discharge valve open.
: b. Initiating flow in a vented system.
: c. Slowly closing a' valve with flow in the line.
: d. Slowly opening a valve to increase the flow in the line.

r -- _ _ ;_--                                                                                                                     ,
b PAGE- 15 L ' li__EBING1ELES_9E_UUGLE88_E9 WEB _EL8dI_0EEB811gNt.
THERMODYNAMICS                                       S _HE8T_IB8NSEEB_8ND_ELUID_ELOW ANSWER:                                             1.15          (1.00) c.
   ,  : REFERENCE-
      -CATAWBA Handou'; OP-CN-HO-FF                                              p.18
;-       193OO6K110'                                              ...(KA'S)
     -QUESTION                                            1.161         (1.00)
      ' MULTIPLE CHOICE:
: During ' a Unit 2 plant cooldown and depressurization with f orced circulation, RCS loop flow indication becomes erratic.                                               What is the'most likely cause of tha erratic RCS loop flow indication?                                                             (1.0) a.-                                   RCP~ runout
: b.                                   RCP cavitation
: c.                                    RCS hot leg saturation
: d.                                   RCS loop water hammer ANSWER                                              1.16          (1.00)
         .b.
REFERENCE CATAWBA Handout OP-CN-HO-FF p.8 through~10
      . WESTINGHOUSE, Thermal'-Hydraulic Principles and Applications to the Pressurized Water Reactor- II, 1982, page 10-54 1 91004K106                                              ...(KA'S)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

i' E 11k__EBIN91 ELE @_gE_NQC6g88_EgWEB_E68NI_QEE88119dx                                                                              PAGE- 16 ll ::* : 7 THERMODYNAMICS                        t _ HEAT _IBSN@EgB_8ND_ELUID_ELQW fDUESTION             1.17                                                 (2.00)
MULTIPLE CHOICE:.
1.
       ' Indicate whether the power range inctrument'will indicate HIGHER than, LOWER than, or the SAME as actual power, if the. instrument has been adjusted to 100% based on a calculated calorimetric'(secondary heat E       balance with the following errors). Consider.each' err-or separately.
: a.           If the f eedwater ' temperature used in the calorimetric was higher than actual feedwater temperature.
l L             b.           If the reactor coolant pump heat correctiori is omitted from-the E
calorimetric.
: c.           If the feed flow used in the calorimetric was lower than actual.
                                                                                       ~
: d.           If the Steam Generator blowdown calculation is omitted from the calorimetric.
ANSWER               1.17                                                (2.00)'
: a.         ' Lower
: b.         . Higher
: c.          Lower.
: d.          Higher REFERENCE CATAWBA Handout OP-CN-HO-SLC p.14 through 17 193OO7K106-               ...(KA'S) dUESTION' 1'.18                                                          (1.50)
Answer the following TRUE or FALSE:
: a.          Volumetric flow rate f or a positive displacement pump increases in the same proportion as the speed increases.
: b.          As VCT temperature decreases, net positive suction head of the Charging Pump decreases,
: c.          Pump runout is the term used to describe the condition of a centri f ugal pump were maximum flow is recirculating to the pump suction.
i

         ;11 L  _EBINglELEQ_QE_NQGLE88_EQUEB_EL@NI_QEEB811gNs                                                         :PAGE' 17
       ^
LIFiERMODYNAd1GSt_HgAT TB8N@EEB_8NQ_E691p_ELQW 7         ,
ANSWER'            1.18         ('1. 50 )
               = a '. - True
               .b.    -False oc . : False
            -REFERENCE
: CATAWBA Handout OP-CN-HO-FF p. 8 through 18 191004K106             191004K112     193OO6K115-                  ...(KA'S)
QUESTION          1.19-        (2.50)
Given the-.following conditions for Unit 2.
Th ' =    621 F-               PR2 Pressure                2235 psig Tave = 591 F                   S/G Pressure                 850 psig JTc      = 561 F
: 1.   . What His the subcooling margin (SCM) of the plant? (Show Work)                                     (1.0; L2.. If plant power is decreased from 100% to 50%, why will SCM change?'
(0.75)
             .3. . Which ONE of the f ollowing conditions would -give a SMALLER SCM7                                     Assume normal expected'temperture and pressure for each case. _Driefly' explain why.                                                                                                (0.75)
: a. SCM associated with stabilized natural circulation to remove decay heat follcwing a reactor trip from. loss of flow.
: b. 'SCM produced when all RCP's are operated at. normal no-load temperature after extended shutdown.
l l.
I i
r

:li__EBING1 ELE @i,QELUQQLE88_EQWEB_EL8UI_QEEB8IlgNu .                                                                                                                                     PAGE ^ 18 "
THERMODYNAMICS                                         t _{jg81_IB8NSEEB_8NQ_ELQ1Q_E6QW L
l .:
l l.:    ' ANSWER-                                L1.19                                                      (2.50) 1-           ->
[         : J :.                        '2235 psig = 2250 psia                                                     (.25)
                                   ;Tsat'for 2250' psia =653'                                                      .F +/" 1F   (O.25)
SCM= Tsat-Th='- 653-621                                                   = 32F.+/- 1F   (0.5) r
: 2.                          Because Th decreases. (0.75)
: 3.                         a.' - ( 0. 25)-
                                    "Coro delta T during natural circulation will approach full 1 cad delta T. Thot.is greater than in the other 2 cases.                                                                                                              (0.5)
(accept " core delta T is larger").
REFERENCE Steam: Tables OO2OOOK509                                           ...(KA'S) l
(***** END OF CATEGORY 01 *****)

2r_iELONI_DEgigN_INpsyDINQ_@GEEIy_8ND_EdEBGENCy_SygIEUS                                                    -PAGE 19
    . QUESTION      2.01.        (1.00)
MULTIPLE! CHOICE:
Whi ch- ONE L of.the following-is-NOT one of the four paths that provide core
       -bypassiflow?.
: a. Upward flow through the ' nozzles in upper support structure flange and core barrel.
: b. Upward flow through the upper internal columns.
: c. Upward flow through the instrument' thimbles,
: d. . Upward flow through the baf fle/f ormer plates.
ANSWER        2.01        -(1.00)
       'b.
i.
REFERENCE
       ' CATAWBA' Handout OP-CN-HO-RVI- p.15
;-      OO2OOOA105-        ...(KA'S)
QUESTION       2.02         (1.00)                                                                                   j LAnswer'each of the following TRUE or FALSE concerning the Diesel Building Ventilation System.
a.-  When the' diesel is shutdown the Essential Ventilation Fans.will automatically stop and the Normal Ventilation Fan will automatically start.
: b. With'the Diesel in operation and a D/G Building fire signal is activated, ALL operating fans will shutdown.
ANSWER        2.02         (1.00)
: a. FALSE                                                                                                        j l
       -b. TRUE
       -REFERENCE                                                                                                         l CATAWBA Handout OP-CN-HO-DG1                       p.3,4                                                          )
064000 GOO 7       ...(KA'S)                                                                                      j l
(***** CATEGORY O2 CONTINUED ON NEXT PAGE *****)
L_______-_--____.-_                _ _ _ _ _ _ - _ - _ _ -     _ - - _

L2i_ ELONI_DggigN_ INCLUDING _S8EgIyiGND_EdgB@gNCy_gygIgMS-PAGE   20
:)
1,          '-
?                                                                                                                                                                            )
l l
                     . QUESTION                      2.03.                        (2.00)-                                                                                  .j 1                                                          .
                                                                                                              .                                                              l Ja.                 State;which discharge collection tanks'the following Chemical and 1 Volume Control System (CVCS) relief valves discharge to.                                              (1.5) i 1.. 600_'psig Ictdown relief. (NV 14, upstream of letdown heat                                                               j e>t chang er )                                                                                                           {
: 2. 300 psig 1ctdown' relief (NV 151,. downstream of letdown heat                                                            j exchanger).
: 3. , -150 psig-seal water heat exchanger relief. (NV 205, downstream seal return filter)
: 6.          .Which one.of the above relief valves has a downstream temperature monitor to indicate when the valve has lifted.                                                       (0.5)
ANSWER                        2.03                         (2.00) a.
: 1. Pressurizer Relief Tank
: 2. Volume Control Tank                                                                 (0.5 each ans.)
: 3. Volume Control Tank                                                                                                  -
: b.            600 psig relief to the PRT (INV14)                                      (0.50)
REFERENCE CATAWBA Handout OP-CN-HO-NV p.                                          9,10,35,5J OO4000K405                                ...(KA'S)
L -QUESTION                                          2.04                         (2.50)
: a.            What are the conditions that will cause a containment spray (Sp) signal to be generated? (Include coincidence and setpoints.)                                              (1.5) b .- . State FOUR conditions that should exist before a portion of the Residual Heat Removal (ND) system would be diverted to provide additional containment spray.                                                                              (1.0)

i 2,___ E L 8NLp E g198_IU CL U DINQ_ @ @E EIL 8dp_ E N E R @ ENC L g y @IEUS                                              PAGE  21 ANSWER                       2.04                   (2.50)
: a. High-High Containment Pressure (0.2)                                         2/4 CTMT PRESS CH (0.1)
                 >/=3.0 psig (0.2)                                 or
                                                                                     '^ .;}-
Manual lor 27(e 3) 1/2 I uubb u L L a 1 In coincidence with (0.3) a Containment Pressure Control Signal (CPCS)
(0.2)                >/=.4 psig            (0.2).     (Coincidence required for either Manual or Hi-Hi Ctmt press initiation.)
: b. O.. _ UL.T!AL,!_h %..?;h V , f_.A .W Containment pressure rising 'r- :.t d l; < .J >10 p si g4-ECCS and NS sst.6 ems operating in recirculation mode                                            (0.25 each ans.)
                ,ERM/         ttt M '8Cm.iru'uu eiwu euuupLublu)                             us u_r the acci dent y > So sy,pf*
Co pr Asy M/T t;.$''uAE > l.2.I'to C wp cocri,J Flee . I e on ELM 2D L vp sa .r 2 /> TOW; FP3hp37 B *Twh REFERENCE cassarn uw,y cper cmt.                                                   .
                                                                                                                 /
CATAWBA Handout. OP-CN-HO-ISE                              p.16; System Description " Containment Spray System-NS"                 dated 7/11/95 p.14 OO5000K110                    026000A301                  ...(KA'S)
QUESTION                     2.05                   (2.50)
State the TWO design features incorporated into the Auxiliary Feedwater System to prevent pump runout.
   ' ANSWER                       2.~ 05                 (2.50)
The isolation MOV on the MDP supply lines to S/G B or C will close automatically (0.5) if the turbine driven pump is operating (0.5) and the MD pump of tha opposite train fails to run (0.5).
(MDP-B supply to S/G "C" isolates if MDP-A fails to start.)
The isolation MOV on the MDP supply lines to S/G B and C (0.5) will automatically close when the associated MDP discharge flow exceeds 74.utreeM. (0.5) (MDP-A supply to S/G B isolates if MDP-A discharge flow                                                                  l exceeds 750"GPM.)                                                                                                               i 7so REFERENCE CATAWBA Handout OP-CN-HO-CA p.14,15                                                                                             j 0612OOK404                    ...(KA'S)                                                                                         (
QUESTION                     2.06                   (2.50)
What are the conditions that will cause a Safety Injection (Ss) signal to be generated?                 (Include coincidence and setpoints and state which signals can be blocked).

12i__E60NI_QE@lGN_ING6UQldG_g8EE1Y_8NQ_ENEBGENQY_gYSIEN@                                                              PAGE 22.
     .e       .
?.
i ANSWER            2.06-                 (2.50)
[High Containment Pressure (0.2)                           2/3 CTMT PRESS CH.(0.1) >/=1.2psig (0.2)
I' ~ MANUAL-(0.25)                                          1/2 Gives one train or 2/2 both trains (0.25)
LPZR LOW PRESSURE (0.2)                                     2/4 P2R PRESS CH:(0.1)</=1845 psig (0.2)
W     -STMLLINE LOW PRESSURE (0.2) 2/3 STM PRESS CH (0.1)on~1/4 STM LINES (0.1) 725 psig. (0.1)
PZR LOW PRESSURE (0.25) and STM LINE LOW PRESSURE (0.25) can be blocked (below P-11 at-1955 psig)
REFERENCE-1 .
: CATAWBA Handout OP-CN-HO-ISE p.14,15 Notes.CN-ECCS-ISE-05 say 2/3 Press CH at 1.2 psig (not 1/4 PRES CH as OP-CN-HO-ISE p.14 says.)
OO6030G015             ...(KA'S)
QUESTION          2.07           '(2.00)
          .                                                                                                                           i State the operation of the FOUR interlocks that exist between the 4160V Essential: Bus' ETA (B), the normal supply breaker GTA(B) and the 4160V Blackout Bus FTA(B).
ANSWER            2.07                  (2.00) i
: 1. The'FTA(B)-feeder breaker from ETA (B) cannot close if the normal supply breaker GTA(B) is closed (0.5).                                                                                   ;
i
: 2. With the blackout bus FTA(B) powered from the Essential Bus ETA (B) and the normal supply breaker GTA(B) is closed, the FTA (B) feeder breaker from ETA (B) will open (0.5).                                                                                   j
* 3.   -To cross tie ETA (B) to FTA(B) the breaker on FTA(B) must be closed y                                                    !
before the breaker on ETA (B) can be closed (0.5).                                                                     j
: 4. With the Blackout Bus FTA(B) crosstied to the Essential Bus ETA (B) and                                                  l FTA(B) breaker . opens then the breaker on ETA (B) also opens (0,5).
REFERENCE CATAWBA Handout          OP-CN-HO-EP                 p.25                                                                      ,
062OOOK401             062OOOK402                    ...(KA'S)                                                               I
(***** CATEGORY O2 CONTINUED ON NEXT FAGE *****)                                                          l

_ _ _ _ _ _ _ _ _ - _ _ _ . _ _ - - - - - - - - - ~
d'
                                                                                         , g                             *"
f                                                     ------
s .' *
                                                                     ,b+ d'                     e
* i
                                       ~
                                          ~              v e
s
                                                                                                                               === -    .
W u                4
               -                  h w
i i*
(      >
           @h           -
1 '
s     .
C   8 U                                                                        5 *;
t0      -
w                                                                       LU e
                                       ""w                                    w"
                                                                                 '                      U
                                  ,Y                m                     M I
                              /
l i
i                                                  I 1
                                                      .         .               i                                                            )
l                                                  1 l                                                   i                                                           i I                                                  I I                                                  3
                                      ~                                                                                           '
l
                            ,                                            El 1                                                  i I                                                  I                                                  :
I                                                   \                                                          '
t
                   ~                                                           g                                                  -
y g                                                     ,
j                                                                 l                                               = 3g i
D                                         3
* 4-                                                 s' 8
w                                   =,i l
i l         W                                                                 s!             '
l l
1~
i I
l              4
                        +
                                      >c~
t

2z__E68NI_DEgigN_INg6UDINg_S8 Eely _GUD_EMERgENgy_SYSIEMS                                                                                                                           PAGE     23 QUESTION                2.08                                                 (2.00)
List FIVE of the SIX AUTOMATIC actions that occur in the Nuclear Service Water (RN) System upon a complete loss of offiste power with a Safety Injection (Sa) and Phase B Isolation (Sp) . signal present. (NOTE:                                                                                                   Assume loss of offsite power, SI, and Sp occur concurrently.)
x harbas.,scm,e %,c,,,
ANSWER                   2.08                                                 (2.00)                                       '' 8t#W#L N84 b4(r tI st, $gjg gg
: 7. M C HA /NL67 Ittler/of VJLyr epw
: 1. All FOUR(4) RN Pumps start
                    ..    ,us , u.n g u 4 m. .ar vu 4uviuutvu                                                      <eivuw g sMcy   e v14f7 /reur!M ..fM,r dugAf#
A ruuan, e ru u a o , eru w oo                     un i
: 3. DN Pamp Matar Cael e.                                             i..l e t tuviulivo vulvua s iris 11 A,                                            2 fin 11 A, 1RN200,
                         -2RN20P' cm k            D/G Jacket Water Cooler inlet isolation valves (1RN232A, 2RN232A, 1RN292B, 2RN2928) open j'E              Splits the Essential Supply Header
* b8L AN h4 Als Prffy7                  //4jjg
        '/,4              Isolates the Non-essential Supply Header                                                                             jo. pj g g. jNM'N/
(Any 5 at 0.4 each)                                   ll ,
g 7o 6 p(g g ny,, , f REFERENCE CATAWBA Nuclear Service Water System Description (RN)
CNSD-0138-01 p.31;                                              Handout OP-CN-HO-RN p.38,39 Discrepancy between SD and Handout p.39, p.25 076000K105                                     076000K402                   076000K403                                 ...(KA'S)
DUESTION                 2.09                                                 (2.50)
: a. State FIVE interlocks or plant conditions that must be satisfied to open either of the Residual Heat Removal (ND) system Train A inlet isolation valves (ND-1B or ND-24).                                                                                                                                   (1.5)
: 6. Explain how Inlet Isolation valve (ND-1B) can be supplied with electric power if the normal supply is lost.                                                                           Include the location where any switching would be accomplished.                                                                                                                                      (1.0)
I i
. _ _ _ _ _ _ _ . _ _                 _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _              ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _             _ _ _ _ _         ____________                            a

i                                                                                         l
' L2t__EL8NI_DE@l@N_INGLUDIN@_gGEgIY_QND_EMEB@ENGY_@Y@IEUS                      PAGE   24
     .-      -                                                                               1 i
f-h ANSWER-        2.09:        (2.50).                                                      j
: a.   .1 . RCS (NCS) pressure must be <385 psig.
: 2. FWST Suction Isolation valve _(FW-27) must be shut.
: 3. Containment Sump Isolation _ valve (NI-185) must be shut. (0.3 ea.ans)
: 4. Safety Injection Pump Suction valve (ND-28) must be' shut.
: 5. Auxiliary Containment Spray Isolation valve (NS-43) muet be shut.
bi  To transfer (ND-1) power supplies unplug the normal supply (EM/D) and then insert the plug'into the alternate supply (EMXC), (0.5) at the-Reactor building penetration in the annulus (0.5).
     ' REFERENCE CATAWBA Handout OP-CN-HO-ND      p.9 through'15 005000K203        OO5000K401      005000K402      ...(KA'S)
QUESTION       2.10.        (1.00)
State the purpose of the check valve NV 36, Charging Line to Loop 'A',
around the normali charging valve HV-32, Loop Isolation.
   = ANSWER        2.10         (1.00) i Prevents overpressurization of isolated charging lines (due to thermal expansion).
REFERENCE CATAWBA Handout      OP-CN-HO-NV  p.33 OO4000 GOO 4       ...(KA'S)
DUESTION       2.11         (1.50)
Describe the following Auxiliary Feedwater System (CA system) interlocks on the f ollowing valves: (Setpoints not required)
: a. CA Condensate Storage Tank supply valve (CA-6).                 (0.5)
             ~b. The Nuclear Service Water (RN) supply valve to the CA system.
(1.0) i

I 3      "
R                                                      &                           R                                                                             .
E
             -                  2                                                               T 5      '
u             ~,''                               A W
e  -
                              $^
A '
3 gg''gL       ' u A M
                                                                       'R E
Y              W U
                                                                                                /
e e
r v
Y
             -                S 8,I                                {TH                         R
                                           ,a
             -          0 0
* 8 A                  "
f
             -          3       9,                  A                              0             I 8                    0 S                        '     0                                           5 4                   5
            -               8                                     L                    t e                   ~
m ]p .
8 4                                                         r
                             '        ' -                         F                                         -
                        ,             {-                                                   !
s
                                                                                                                                         /                    n                    O Ts o-M
* 3 2                                      e                     S
                                                                                                                                                                                     . w s,,
                       -g                                                                                                                                                              R h                                             g 1
7                           '                 L 0T 5 2      3 5 .A O                                                3
                                                                                             ~
l
                                                                                                                                                         ,.         . 2 H 2 u                          '                                                                           2R D   C M
                                     ~
h        O
                                                                                             ~
F&Ng g o"
                                                                                                                                    $yy                I            _                    2-c
    "    $ )M l
A'                  g g
s o
D
                                                                                               *d                  9                    C" yL A
2 7        N y                                   )gp           p eg g                                                         sg                                                                  1 5
4 4
1 M                                    2 e
                                                                                                                                        }0 g N-
                                                                                                                                                                   ,                    h              Qb rh 3                                4                                                           A              - : j
[
0 1
8 p
u                                       m2                      Ou.s3 g
l g,-l Q=          -
                                                                                                        ~                           _
t c
v 9m S
                                                             $            b {'' 9                                                m                                                       -
    = ,
L A                 s A
G W
c M,
OK
                                                                               ,       3 2
m ga q m                       T H
R f               g,[
[
O s
a      H M                 G                              RT , N                                                                                        3 2 R         y E                                    r 0                    , ,                                                                    0 0           -
E          g O                                                          ,
2 2                            _
_            H                                                  2/                                                                              :
T                        u                        s e    S                       Y
     .                                                .                                                   C          t 1
      .                                             S                                                      V         e 4
=
I                                                                                                               r 7b _ , d "M4 1
2 9
O Or                                                                                                                   ,                                                                           .
oa s r     .                 ^ '            .e      ',                                                                   ,                            0' o                                         s      s n
                                                          .l s g e IN l1, I J-- ,                 ,
3,i                                            9igiis
        -,        g
                          ^
c,                                -
xvs
                                                                                                   ,5                                                                                                                           -
e' a                                                                                          .2 H                                                                                                                     -
g .i,.
s,                            ,           ,
1               l N'                                                 Ng                           n M                    #
3                            M9s"e                                      m                                            u
  , #3                                                   "l                  3                                          I H                                                                 4 1E             e2                                                                                                         E
                                                                                                                                  -(
1                                                                                                    T
(                                                                                                                                          -                        nsy
( 22A M M.,"'          n                              '
s                        '
t s
I' 4              m                                                 A 4                                                                t 1U '                  -           e
                                                                           =e_
                                                                                                      ?                        _             , s ?--
                                                                  .       A O N                10     2             9_,
D 'C                      UY L           P P AAR OO                                              s. _     -                        2 g P O ORP O O L L ZS                                 -
                                                              ,e O L
P es Cs Nu                                                    YP P
9U D          ,
NE         ,
A K A, TA sW*p

[2i__E60NI_DE@lGN_INC69 DING _BGEEIy_8ND_EMEBGENCy_@y@IEd@                    PAGE' 25
    ' ANSWER.        2.11          (1.50)                 [
      -a. Automatically. closes on allow-low level in the CA CST tank. (0.5)
                                                                              ~
: 6. The RN supply valves auto open on low suction pressure for CA pumps (0.5) if CA system has auto started (0,5).
REFERENCE CATAWBA-Handout OP-CN-HO-CA p.             16,17 061000K401          ...(KA's)
   . QUESTION        2.12          (2.50)
Concerning the Reactor Coolant Pump (RCP) . seal packaget
: a. What is the normal pressure drop across each of the         different seals?
(0.75)
: b.      Why must the operator observe and maintain the specified minumum pressure across the #1 seal?                                          (0.75)
: c. What are 2 possible discharge points for any leakage that goes through the #3 seal?                                                    (0.5)
: d.      The #1 seal bypass is designed to be used only when NC system pressure is between what limits?                                                (0.5)
    . ANSWER         2.12          (2.50) a..    #1--------2200 psi          (Accept 2100 - 2300 psi)
               #2--------47 psi            (Accept 15 - 50 psi)
               #3--------O psi             (Accept 0 - 5 psi)             (0.25 ea.)
b.-    Must maintain minumum (200) psid so seal surfaces will not contact
:each other (prevent face rubs).                                        (0.75)
: c. Discharge to Containment ATMOSPHERE (0.25) or NCDT (0.25).                   a
: d. Greater than 100 psi (0.25) and less than 1000 psi (0.25)
REFERENCE CATAWBA Handout         DP-CN-HO-NCP.p. 14,15,24;      CN-PS-NCP-9 OO3OOOK103          ...(KA'S)
(***** CATEGORY O2 CONTINUED ON NEXT PAGE *****)
= _ _ _ _ _ . _ _ _ _ _          _     ___

    '2z__E68MI_pESl@N_INCLUDIN@_g8EEIy_GND_EME89ENCy_Sy@IEd5                         PAGE   26 1
      ...     +                                                                                l
                                                                                               )
QUESTION             2.13-       (2.00)
{
       .a. Describe.the design feature that prevents KC Containment I sol ati on -
            = Valve (KC429B) f rom repositioning during a flooding event.              (1.0)
Lb. Exp1'ain how the open-shut position of Containment Isolation Valve
!            (KC429B) can be verified if a flooding event renders normal position              1 indication inoperable. (Include any associated actuation signals)
(1.0) i l . ANSWER                2.13        (2.00)
: a.  (The= control circuit to open valve.KC429B contains a normally closed contact which opens during a flooding event to) freeze (KC4298) in the closed position ,JD<dT. (/,o )
: 6. A computer program (OAC) records valve position prior to submergence (0.5) and di splays this position via the Utility Typer (0.5).
REFERENCE                                                                              !
CATAWBA Component Cooling Water (KC) System Description (CNSD-0142-01)-
p.7,S OO9000A401'            008030A301      ...(KA'S)
QUESTION ~2.14                   (2.00)
Answer the following concerning the Steam Generator PORVs.
: a.        If the plant is stable at SO% power and all four S/G PORVs are fully opened, what would the new steady state reactor power be?
(Assume no.other operator action)                             (0.5)
: b.        How is the PORV operation and indication affected when both PORV breakers located behind MC-6 in the Control Room are de-energized?
(0.5)
: c.        What is/are the source (s) of power used to operate the S/G PORVs in AUTO and in Manual?                                        (1.0)

25 iEL8NILDESleNi1NGLUDIN9_E8EEIy_GNQ_EbEBGENgy_SygIEUS                              PAGE                27-
     ~ ANSWER        2.14L      . (2. 00 )                                                                         -
: a. 90%: +/- 2%      (0.5)
      -b. Denergizing,the.two breakers causes control of'the PORVs'to fail to the AUTO position (0.25) and indication-for " AUTO / MANUAL" is lost (CWF)
(0.25)'
U"     c.' Instrument' air.is'the-normal source (0.25).of power for Manual and Auto
            .(0.25) operation.- Nitrogen (N2) is the backup sourco (0.25) of power and only supports Manual ~ operation (0.25)
       ' REFERENCE CATAWBA Handout OP-CN-HO-SM        p.10 035000K602-        ...(KA'S)
(***** END OF CATEGORY O2 *****)
t-

43i__INDIBud5NIg_eND_CONIBg6@-                                                                                                                                                                               PAGE                   28 l
  ' QUESTION- 3.01                                                    '( 1. 00)
P f                .
MULTIPLE CHOICE:
Which DNE of'the following' statements concerning the Steam Generator Level Control system is correct?
           'a.. Both Unit 1 and Unit 2.use an auctioneered high Nuclear Power input signal for control of the Feed Rpgul ating Bypass Valves.
Rb . Neither Unit l'nor Unit 2 use an auctioneered high Nuclear Power input signal for control of the Feed Regulating Bypass Valves.
: c. Unit i level error signal - is developed using a Nuclear Power input signal.
: d. Unit 2 level error signal is developed using a Nuclear Power input signal.
ANSWER          3.01-                                                (1.00)
C.
REFERENCE                                                                                                                                                                                                                             j CATAWBA       -CN-IC-IFE-1;                                                                         OP-CN-HO-IFE p.9 035010A301~                               035010K401                                                                                                         . . . (KA' S)
QUESTION        3.02                                                 (2.00)                                                                                                                                                              !
i State whether the following annunciators or systems receive an AUCTIONEERED HIGH Tave, AUCTIONEERED LOW Tave or NEITHER input signal.
                                                                                                                                                                                                                                           'l
: a. Steam Dump Plant Trip Controller                                                                                                                                                                                           l i
Interlock C-16 (Inhibit Turbine Load)                                                                                                                                                                                      I b.
I I
: c. Permissive P-12 (Steam Dump Block)
: d. Rod Insertion Limits i
1
: e. Load follow meter on MCB 4

                      '[! l 13t__INSIBUNENI@_GNQ_GQUIBQLE                                                                                                                                                                                               PAGE             29 u,        o                                              ,
ANSWER           ' 3.' 02..                                                 '(2.00)
                                                                                                                                                                                                                                                                     \
Ta ^. -  AUCTIONEERED HIGH:Tave                                                                                                                                                                                                                           )
: b. AUCTIONEERED LOW.Tave                                                                                                                                                                                                                             i
           .c.. NEITHER                                                                                                                                                                                    (0.4 Each Ans.)                                       1
: d.   .;AUCTIONEERED'HIGH Tave (NEITHER if. assumed Tave signal nulled)                                                                                                                                                                                 i Le.- AUCTIONEERED LOW Tave l
REFERENCE.                                                                                                                                                                                                                                             l
           . CATAWBA Handout'.OP-CN-HO-IRX p.9; DWG CN-IC-IRE 1016000G007                                016000K403                                   ....(KA'S)                                                                                                                                                        j 1
         'OUESTION           3.03                                                      ( 1.' 00 )
Answer the following TRUE or FALSE concerning the Pressurizer Level Indication System.                                                                                                                                                                                                                                     ;
1
: a. A 17%. bistable that failed' low would initiate a maximum charging flow 1 signal.
:b. If the low pressure (impulse). side of the channel 2 differential pressure detector ruptured, then indicated level would read lower than actual level.
l
       'LANSWER             -3.03                                                      ( 1. 00 ) -
: a. FALSE                                                                                                                                                                                                                                             l b.-   TRUE' REFERENCE
           . CATAWBA Handout CN-OP-ILE-HD- p.3,4; OP-CN-HO-NV                                                                                                                            p.B; CN-PS-ILE-2; and                                                       ,
           .CN-IC-ILE-21' 011000A101                              011000K301                                    011000K404                                                                     ...(KA*S) 1 OUESTION           3.04                                                      (2.50)
State the THREE separate conditions that will activate the "RPI at Bottom L             Rod' Drop" annunciator under nomal conditions. (Include setpoints where applicabl e. )
l' it i
l-
   . .,-                            _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                                               _._1..___                         _ . . _ _       __   __. _ _ _ . _ _ _ _       __   _ _ _ _ _ _ _ _ _ _ _ _
                                                                                                                                                                                                                                                         ._. . . ._ j

i N-        . . .                         .       .                                                                                     -
          %3t __INEISUdENIQ_6ND_GQUIBQLE'                                                                                          . PAGE        30.
ANSWER                             3.04           (2.50).
[
              ' 1.                  ;Any Shutdown or Control Bank A rode (0.25)- that is within six steps i                                       of the bottom of its travel (0.25).
: 2. . Any Control Bank B, C, or D (0.25) within six steps of the bottom (0.25)'and the other rods in the same-bank and group (0.25) are greater than six steps- f rom the bottom . (no bottom LEDs). (0.25) .
: 3.                     Any Control Bank B,C and D (0.25) within'six steps.of the bottom (0.25) and rods which should'be sequenced out after that rod (0.25)'
are off the bottom (0.25).
REFERENCE r        , CATAWBA Handout                               OP-CN-HO-EDA.                p. 7,13
                  '014000K101                          014000K403                    ...(KA'S) l QUESTION                           3.05           .1.50)
(
                ~ List the'THREE'permissives which are supplied by the output of the Power Range Nuclear Instrumentation.                                       Includo setpoints and coincidence.
ANSWFR                             3.05           (1.50)
P-8 (or single loop loss-of-flow) permissive (0.2)
                                     -2/4'P.R. (0.1)             >/= 4S% (0.2)
P-9 (or reactor. trip on turbine trip) permissive (0.2) 2/4 P.R. ( 0.1 ) '     > 69% (0.2)
P-10~(or. low power) permissive (0.2) 2/4 P.R. (0.1)        >/= 10% (0.2)                                                                         3 REFERENCE CATAWBA Handout OP-CN-HO-IPX                                       p.18;                    OP-CN-HO-ENB p.16 015000K407                          ...(KA'S)
DUESTION                           3.06           (2.00) a.. .What condition (s) are required to enabic the P-4 permissive?
                                       .(LIST TWO COMPONENTS AND THEIR REQUIRED POSITION)                                               (0.75)
: b.                    What are the actions that the P-4 permissive initiates? (LIST FOUR ACTIONS and ASSOCIATED REQUIRED CONDITIONS as appropriate)                                    (1.25)

c l-PAGE  31 13g__INSIBUMENI@_8NQ_ggNIBgLS ANSWER.        3.06         (2.00)
: a. Reactor trip-breaker (0.25) and its bypass breaker (0.25) are both open (0. 25)-   (Train A or' Train B)
: b. 1. Trips.the main turbine (0.20)         h. O^t#4yj kggjg (,                                                                    y
: 2. Actuates Feedwater Isolation-(0.20) if Tavg'is low (less than 564)
: 7. 20utt i.m.*9Mme Por,pt
: 3. Arms the condenser Steam Dumps (0.20) 7, 4, cp g
: 4. Places Plant Trip Controller in service    (0. 20)
: 9. dfff* A'UMA4VM
: 5. - . Permits an SI to be reset (after 60 second delay) (0.20)
      . REFERENCE CATAWBA Handout OP-CN-HO-IPX p.10,        OP-CN-HO-ISE     p.15,17 012000K610          ...(KA'S)
QUESTION       3.07         (2. 25)-
Answer the following concerning "NCS Overpressure Protection" at low
      . temperature.
ar   What'are'the NCS prequisite conditions required for activating
           ,NCS Overpressure Protection?                                                                                                      (1.0)
: b.   " TRAIN B" of the NCS Overpressure Protection system has been enabled from the MCB with NC system at 250 degrees F and 250 psig.                                                                The PORV Mode Selector Switch is in AUTO. STATE how Train B of the NCS Overpressure Protection automatically operates as NC system Temperature and pressure increase above protection setpoints.                                                                     (1.25)
ANSWER         3.07-        (2.25)
: a. Low temperture protection is enabled when NCS temperatures is between 300 F and 295 F (0.25) and pressure is less than 400 (360) psig (0.25) and the keylock switch on the MCB (0.25) is moved from the NORMAL to the-LOW PRESSURE position. (0.25)
: b. When WR loop C (0.25) pressure (0.25) increases above 400 psig (trips B/S) (0.25) PORV-32B opens (0.25). If temperature increases above 300 F the system disarms (0.25) (not enabled) .
2 s'

l PAGE   32 lsi__INSIBQMENIQ_8NQ_QQNIBQLS p   1 REFERENCEL
    . CATAWBA Handout              OP-CN-IPE-HO p.10,11 010000K403                 ...(KA'S)
  -QUESTION                3.09       '(2.50) l
: a.         Refer to figure 3.1 and list the. inputs to the Main Feedwater Pump Speed' Control System at points (1) through (4).
(0.75)
: b.         What are the setpoints for NO LOAD and FULL LOAD programmed D/P for each UNIT.                                                               (1.0)
: c.         State if Main Feedwater Pump speed initially INCREASES, DECREASES or REMAINS THE SAME if the D/P Programmer fails HIGH.. EXPLAIN your answer.                                                                  (0.75)
ANSWER                  3.08        (2.50)
: a.            (1)    Density compensated (0.15) steam flow (0.15)
(2)    Feedwater Header Pressure (0.15)
(3)    Steam Header Pressure (0.15) (2 and 3 may be reversed)
(4)    Actual D/P (0.15)
: 6.         UNIT 1         NO LOAD   D/P-45 psi (0. 25) FULL LOAD D/P. e" psi (0.25)
UNIT 2-        NO LOAD   D/P-BO psi (0. 25) FULL LOAD D/P 225 psi (0.25)
: c.           INCREASE (0.25)- Programed D/P great er than Actual D/P would cause MFW Pumps to increase speed (0.25) to raise actual D/P to match Programed D/P (0.25)er gro Wthe>< if CAWJipart wunc 12e JfC US c idwr, REFERENCE CATAWDA Handout OP-CN-HO-IWE p.7,8,10;                      CN-IC-IWE-1 035010K101.                035010K401             ...(KA'S)
DUESTION                3.09        (2.25)
: a.         What are the input signals required to enable the P-7 interlock?
Include setpoints and coincidences for the input signals.               (1.0)
   .b.           State the reactor trips enabled by the P-7 interlock.                     (1.25)

e OLAt34 ton    34)B
      ..                                                  page  41a 1
O
             \
aJ                                            '
3$ .
I D                      $
c                            s n,     1p                   f p                    a I
s*     !
s   -
h   -
fi Gurt t . 3
* 1

   '3 2__IUMIBudEUIg_8ND_CgNIBg63                                                                   PAGE                         33 ANSWER                       3.09            (2.25)
: a.           The P-7 interlock is satisfied (unblocks at power trips) whens (1)  P-10 Interlock is satisfied- 2/4 Power Range Channels greater than 10% power. (0.5) or (2)  P-13 Interlock is satisfied-1/2 Turbine Impulse pressure channels greater than 10% full load. (0.5)
: b.           When the P-7 interlock is sati sfied the following reactor trips are unblocked:
(1)  Pressurizer High Level (2)  Pressurizer Low Pressure (3)  La    NC   'l o : Two (1) Loop j.*it 6f }~Le w (4)  NCP Undervoltage (5)  NCP Underfrequency (0.25 each)
REFERENCE CATAWBA OP-CN-HO-IPX p.17,18;                                    CN-IC-IPX-24 012OOOK406                         012OOOK610          ...(KA'S)
DUESTION                     3.10            (2.00)
State the plant conditions that would initiate and terminate each of the f ollowing Main Turbine Runbacks separately (Setpoi nts and rate of runback required)
: a.          OPdT and OTdT Runback.                 (1.O)
: 6.          Feedpump Trip-Turbine Runback.                   (1.0)
ANSWER                       3.10            (2.00)
: a.           Inputs to the Power t< Temperature Runback are either DT Delta T (0.2) or OP Delta T. (0.2)                 The setpoint is the Delta T setpoint minus 3%
(C.2).           Turbinn load is reduced 133% per minute for 2.3 seconds every 30 treconds (10.2%/ min)(0.2) until the initiating conditions clear (0.2).
b            The turtzi-rre runryMck at 20%-per minute-(OI2) until' power drops-bGlow 00 30 secondp hive passed / C'.2) sinc / power dropocd below 80/.
                                             ~
70% f0 (p.4).72) /
E b'%l # '' . f""M4 THw H & & m w &
s,c 1
z m ,
a jdHnr Ma seca up m z,,,u ,g,                                            i
                                                                                               *ma s
y p g, ,g,,,(,_g) e A M+D If leu T w 7 o pl (r,1 s ),
L_      _____ _

y                     .
s -                               .v         ~
h281__INSIBydENIS_huQ_GQNIBQL@:                                                                 PAGE   34 h              .;        .
1 REFERENCEL        .                        .   ..
CATAWBA CN-GEN-EHC-27 dated 4/19/88 LOP-CN-HD-IPX p.15                                                                ;
lO45000K412               . .. . ( K A ' S )
F         ,
iQUESTION            3.11'                (2.00) l a ~. List the.TWO' conditions required to ENABLE the. steam dump Load Rejection Controller.                                                        (0.4) 4        th .. ListLthe.1HREE conditions. required to ARM the Atmospheric Dump valves.                ,
(0.6)      l
          ,c.
                    'To' arm the Condenser Dump; valves the.C-9 interlock and at least one additional condition.must be satisfied.
: 1. List the TWO conditions that satisfy the C-9 interlock.                      l
: 2. List the THREE additional conditions, any of which together               I with C-9 could arm the. Condenser Dump valves.                  (1.0) l 1
i
: ANSWER            3.11                 (2.00)
U                                                                                                           i Ea .1      Steam Dump Select switch.in Tave position (0.2)                                        )
                    .NO'P-4 (Reactor Trip). (0.2) 1 b.. Steam Dump Select switch in Tave position (0.2)
                    ~C-7B Load. Rejection Signal ( 0. 2)-
p               lN0lP-4 (Reactor Trip)                 (0.2)
          .c.:       1',    C-9 is satisfied if Condenser vacuum greater 20"Hg (0.2) and 1/4,RC pump breakers closed (0.2).
: 2. Either a Train'A permissive P-4 (Reactor Trip) (0.2) or a C-7A Load ' Rej ecti on (0.2) or the Steam Dump Select switch in Steam Pressure position (0.2).
REFERENCE
           ' C ATAWBA ' CN-IC-IPE-16;.                 OP-CN-HO-IDE p.3,4,5 LO41020K417             041020K603-                  ...(KO'3)                                   :
iil
       ; QUESTION. 3.12                          (2.00)
;/ fu Describe the op er ation of the interjotka associated with the Reacter Trip 1 ' Breaker ri and. the Reactor Trip Bypasu Bro-skers.                                                      j J
l l
o I

at__INSTRUDENIS_8ND_GONIBQLS                                                                                       PAGE          35 ANSWER         3.12          (2.00)
Closing the Reactor Trip Bypass Dreaker of one train (0.25) while the opposite train is in test (0.25) will result in the automatic trip of both Reactor Trip Breakers (0.25) and both Reactor Trip Bypass Breakers (0.25).
Closing the Reactor Trip Bypass Breaker of one train (0.25) while the Bypass Breaker of the other train is closed (0.25) will result in the automatic trip of both Reactor Trip Brea,<ers (0.25) and both Reactor Trip Bypass Breakers (0.25).
REFERENCE CATAWBA Handout PP-CN-HO-IP/ p.17 OO1000K603            012OOOK401         ...(KA'S)
QUESTION       3.13-          (2.50)
If a circuit card in Rod Control Power Cabinet 1 AC vibrates loose:
: a. How would rod motion be affected?                                                                                (1.0)
: 6. What local and remote alarms are actuated?                                                                       (0.5)
: c. How are the various CRDM coils affected?                                                                         (1.0)
ANSWER         3.13           (2.50)                        O,2
                                                             -(
: a.      All  rod mat a mn rtT(auto +C%-P) and manual) .M+rt1 is stopped (0.2).
The Operator can move other wiidivi+se+ banks ( O'. 2 ) not powered f rom Mw#.
If,C  : 2 mt - ' . 2 >- Affreffi) c newfr( o,2) w >p pp>M fway-(o,2')
l
: b.      The Urgent Alarm lamp on the Power Cabinet is energized. (0.25)                                                A I
Control Room " Rod Control Urgent Failure (Power Cabinet)" annunciator i s activated. (0.25)
: c.      The 1tft coils (0.2) are deenergi zed (0.2) and both the stationqry (0.2) and movable (0.2)ycails are energized at reduced,(0.2) current                   g l
(4*4 amps.)                 pgjp,g                                                     gg L   REFERENCE l  CATAWBA Handout         OP-CN-HO-IRE p. 13,16,19 OOr.OOOK407          OO1050K401         ...(KA'S)
(t**** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
[                                                       _  _      _   . _ _ _ _ _ _ . _ _ _ _ . .   .__._.___________.___________._________J

i-sz__1USIBUMENIS_6Np_CQNIBOLS                                                                                   PAGE                      36 QUESTION                          3.14          (2.50)
: a.               Describe how the "High Flux Alarm" setpoint is determined for the Shutdown Margin Monitoring System after the reactor has tripped or shutdown.                                                                                            (1.0)
: b.               When the Shutdown Margin Monitor is enabled and the high flux setpoint is reached, what THREE plant actions will automatically occur?                                       (1.5)
ANSWER                            3.14          (2.50)
: a.                 (The decreasing neutron flux is continuously tracked) and the alarm setpoint is automatically calculated (0.5) at four (4) times the actual source range countrate (0.5).
: b.               Reaching the high flux setpoint initiates the following action:
A trip signal is sent to both reactor makeup water pumps. ( 0. 5 )
The charging pump suction valvas (NV188A, 189B) from the VCT closes.  (0,5)
The charging pump suction valves (NV252A, 253B) from the FWST open.
(0.5)
REFERENCE CATAWBA Handout                          OP-CN-HO-ENC p.7 OOOO24A206                             01500K106/      ...(KA'S)
( 50 DUESTION                          3.15          f-1,5C L The DP cells used with the Reactor Vessel Level Indication System RVLIS) are located outside of containment.
Dr.cribc 'WO INLIC ca. , vim.du           (Aimludiuy i n ai.el l at i on - l oc atrcyn s ) thuL
      %.                                                                         3 of     I:VLIC s ; n c im1-144+e-tree--
[d,/j, ar-e-desgned-to-1nR+gete-the 4                    ert+t :.,; d e smt;;i - ~ m t .       con sequence:
m
                                                                                                                         - ' 1. ;)-
l
   \O
: b.                Explain why Resistance Temperature Detector (RTDs) arre installed on the RVLIS instrument lines locatad inside containment.                                               (0.5)                       j i
1 1
_.-_.m_   _ _ _ _      .___m._

3z__INSIBUMENIg_8BD_CONISQLg                                                                        PAGE 37 ANSWER                              3.15        (1.50)
: a.          1.               The sensor bellows installed between t         C system (impulse lines) and the capillary lines inside c         inment  (0.25) are equipped with a check valve which prevente       >akage should a capillary line break (0.25).
: 2.                 Hydraulic iso - rs insta      =d   et e rr  he capillary lines inside containme    and the trant.-     e    ou. side containment (0.25) prov'    automatic contai 1 ment isol ation should the line downstream r    ure (0.25).
: b.        RTDs are used to correct for fluid der.aity changes in the sensing lines (resulting from changes in Containmer. . temperature) . (0.5)
REFERENCE CATAWBA Handout OP-CN-HO-CCM                          p.5,6 016000K101                           ...(KA'S) i
(***** EMD OF CATEGORY 03 *****)
1

L     ,
14D ' PROCEDURES _ _NgBMALx_8BNQBM861_EMgBggNQy_GND'                                           PAGE                     38-7    88,9196991CeL_G9 NIB 96 1 QUESTION       4 .01       (1.00)
MULTIPLE CHOICE:
As~ currently used in CATAWBA Emergency Procedures,'which DNE of the following definitions.-is correct?
: a. A' ruptured Steam Generator has.a feed line or a st'eam line break.
J. A-faulte'd Steam Generator has one or more broken tube (s),
: c. A non-faulted-Steam Generator does NOT have a feed line or 40 steam line break.
d.. A non-ruptured Steam Generator does NOT have a broken tube or a feed line break or a steam line break.
ANSW5R        '4.01        (1.00)
C.
        ' REFERENCE CATAWBA ~ Handout   OP-CN-HO-EP1 p.9 035010A201        035010G015      ...(KA'S)                                                                               l
    . QU5STION       4.02.       (1.00)                                                                                           ,
        . MULTIPLE-CHOICE:                                                                                                        i
         'Which.ONE of the following Portable Radiation Monitoring Instruments is                                                 )
        'used primarily for determining levels of contamination on equipment                                                      l
        'and/or personnel?                                                                                                        ;
I'
: a. RO-2A I
: b. PNR-4                                                                                                        j l
L               c. PRM-6                                                                                                        i L                                                                                                                               .l
: d. RM-14                                                                                                        ;
1 l
[                                                                                                                                 i L.
L o_                                      -_           _ _ _       - -                           -       .

 +Ldc__EBQGEDUBES_ _NRBdebu_GENOBdB65_Edg80ENGy_GNQ.                                                                                            PAGE 39
       ',    .             ESG.QlOLOGIGAL CONTROL'                                                     .
E LANSWER-                                        4.02                     '(1. 00) ~
d'.
REFERENCE-                                               '
CATAWBA Handout -OP-CN-RAD-HP. p.74 through 86' 016000 GOO 4                                        194001K103                       . . .- ( K A ' S )
 !-     .LOUESTION. 4.03                                                          (1.00)
          . MULTIPLE CHOICE:
LAdverse' Cont'ainment Conditions (ACC) are established when ONE of the following' conditions exist.                                                        Choose the correct one.
ca.-                      Pressurizer pressure is less than 1845 psig.
: b. . Containment. pressure is greater than to 3.0 psig.
: c.                    'The Hydrogen concentration in Containment is greater than 4%.
: d.                        Can'tainment temperature is greater than to 120 degrees F.
ANSWER                                        4.03                      (1.00)
           -b.
REFERENCE CATAWBA Handout                                            OP-CN-HO-EP1' p.20;                        EP/1/A/5000/D1 p.6 (Retype #7);
L                                                                      EP/1/A/5000/1C p .1.                        (Retype #5)
OOOOO9A211                                          ...(KA'S) pE '
.r            >
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
: 4. PROCEDURES - NORMALt _8BNgBMAL2_gMg8GENgy_8ND                                                              PAGE  40 RADIOLOGICAL CONTROL-QUESTION           4.04.                   (2.00)
:TRUE or FALSE 7
      . Answer the f ollowing TRUE or FALSE relating to the conventions associated with-the use of-EMERGENCY PROCEDURES (EPs),
: a.        If the actions required in the Response Not Obtaine_ column cannot be performed or are not successful, and further contingency instructions are not provided, the operator must repeat-this step
                        -until the required actions are successfully completed,
: b.        Unless otherwise.specified, a required task need not be fully completed before' proceeding to the next instruction; it is.enough to.begin the task and have some assurance that it is progressing satisfactorily.
: c.        Even after a transition.to another procedure, the steps begun before the' transition was made must'still be completed, but not to delay 'the transition,
: d.         High level' steps describe the task to be performed while substeps are denoted by number if order is important and by letter if order is not important.
ANSWER             4.04                    (2. 00)
: a. FALSE
: b. TRUE
: c. TRUE
: d. FALSE REFERENCE CATAWBA Handout OP-CN-HO-EPI                                         p.7 through 12 l       194001A102                 ...(KA'S)
H
(***** CATEGOR) 04 CONTINUED ON NEXT PAGE *****>                                                 l
    -             _ _ _       _ = _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ .

14[__ PROCEDURES - NORMAL1 _SBN9BdSL 2_EMBBQgNgy_ANQ                                                                                                                                                                                              PAGE- 41 a,~
RADIOLOGICAL
_QQNTRQL
                ~ QUESTION.. 4.05                                                                                            (1.50)
                                                                                                        ~
                              .In accordance with Unit.1 Technical Specifications, complete the following-
                      ' statements:.
: a.                  Minimum baron' concentration in.the NC system.during refueling operations shall be__________________ ppm.                                                                                                                                                                (0. 3 ) .
: b.                 Each Cold Leg JInjection Accumulator nitrogen cover-pressure _shall i?                                                       b e a t ' l ea st __________ ________p s i g .                                                                                                                                                            (0.3)l
                                    .c.                  Primary containment internal. pressure shall be maintained between
                                                       .__________________Psig and __________________psig                                                                                                                                   .           (0.3)
: d.                 The mqximum ice condenser ice bed temperature shall be,less than or equal to _________________,_ degrees F.                                                                                                                                                                    (0.3)
: e.                 Whenever. primary or secondary side pressure of the Steam Generator is greater than 200 psig, the temperature of both fluids must be greater than'__________________ degrees F.                                                                                                                                                                     (0.3)
ANSWER                         4.05                                                                 (1.50)
: a. 2000
                              'b.-  585-
: c.   -0.1,0.3
: d. 27
: e. 70
                            . REFERENCE CATAWBA TECHNICAL SPECIFICATIONS 3/4.9.1; 3/4.5.1; 3/4.6.1.4; 3/4.6.5.1.c; 3/4.7.2 OO4000 GOO 5                                  OO6000 GOO 5                                                                          022000G005                ...(KA'S)
DUESTION- 4.06                                                                                       (1.50)
Enclosure l'to EP/1/A/5000/01, " Reactor Trip cr Safety Injection", lists
                              <two requirements for positioning the NV Pump A and B Recirculation L! solation Valves (1NV-202B and 203A).                                                                                                                 State the TWO requirements and explain the reason for each one.

i.
   '4.                                         PEOCEDURE@ - NORMAL x_8BNORdAL _t EMERGENCY _AND                                                                                                                                                                                                                                     PAGE         42 RADIOLOGICAL CONTROL ANSWER-                                                                                      4.06                                       (1.50; To ensure ma:<imum flow to the NC loops, (0.25) the recire isolation valves are closed-(0.25) if NC pressure is less than 1500 psig. (0.25)
To' ensure NV pumps have a recirculation path available (prevent operating             .
pumps against shut offhead) (0.25) the recirc isolation valves are opened (0.25) if NC pressure is greater than 2000 psig (0.25).
REFERENCE
    . CATAWBA                                                                                    EP/1/A/5000/01                                                               p.21 (Retype #7); VIEW GRAPH "EPOI ENCLOSURES" to
                                                                                          -OP-CN-HO-EPI OO6020K401                                                                                    ...(KA'S)
   -QUESTION                                                                                      4.07                                       (2.00)
: a.                                    Stat'e the NCP Trip Criteria as listed in Enclosure 1 to EP/1/A/5000/Li.,
                                                    " Reactor. Trip or Safety Injection."                                                                                                                                                                                                                                             (1.5)
: b.                                        If forced flow caused by running NC pumps through the core promotes cooling, what is the basis for tripping the NCPs during a Loss of Coolant Accident?                                                                                                                                                                                                                                                                  %
06 ANSWER                                                                                        4.07                                       (2.00)
: a.                                       If SI flow is indicated (0.5) and NC subcooling less than or equal to zero degrees F (0.5)                                                                                                                                                             If "KC Supply Header Flow to NCP Bearing Law" annunciator is alarming (0.5).
: b.                                     Tripping the NCPs during a loss of coolant accident (SB LOCA) prevents depletion of the NC inventory (0.5) (which causes unacceptable peak clad temperatures).
REFERENCE CATAWBA Handout                                                                                   OP-CN-HO-EP2                                                                                                                      p.16,22; EP/1/A/5000/01 p.21 (Retype #7)
OOOOO7A104                                                                                    OOOOO9K313                                                                                                                    ...(KA'S)
(*****                            CATEGDRY 04 CONTINUED ON NEXT PAGE *****)

thz__EB99E99BES;_N9Bd861_8BN9Bd861_EMEBgENGy_8ND                                                      PAGE     43 iB8,D196991986_G9 NIB 96
  ' QUESTION                 4.08.        (1.00)
Given the following summary of Critical Safety Function (CSF) status trees while performing EP/1/A/5000/IC3 " Transfer To-Cold-Leg Recirculation":.
: 1. Subcriticality                            . Green                                                   l
: 2. Heat Sink                                  Yellow
:3. Containment                                Red-
: 4. ' Integrity-                                Orange
: 5. Inventory                                 Green
                        '6. Core Cooling                               Yellow List'tSe orJer in1which the CSFs'should be addressed, assuaing that ALL CSF
      .not satisfied require action.
ANSWER                   4.08         (1.00)
         .3 ,4 ,'6,2                    (0.25 for each CSF in proper order)
       -REFERENCE CATAWBA Handout          OP-CN-HO-CSF    p.5,6 OOOOO9G012            ...(KA'S)
QUESTION                 4.09         (1.50)
Step D.2 of EP/.1/A/5000/03, " Lass of All AC Power", directs the operator to verif y that the NC system is isolated.            List the valves that must be checked or verified to accomplish this step.               (Valve numbers not
         -required.)
h-
                                                                                                                               +
I
______ __ _ _ _ _ _ _ - _ _ - _______-___-________ _ _ - - ___ _ - _ a

4i__EBQGEDUBES_:_bOBd86t_8BNQBd86t_EMEBGENQY_8NQ                                                      PAGE        44
           .RADIOLOGIG8L_QQNTBQL l
l ANSWER                               4.09          (1.50)
      -----Pressurizer PORVs closed (0.3)
      -----Letdown isol ation valves - closed (0.3). (LTDN ORIF Outlet
: Cont. Isol INV-10A, 11A, 13A and LTDN to REGEN HX i sol INV-1A, 2A)
      -----Excess! letdown isolation valves closed. (0.3) (Loop C to Exs LTDN HX Isol INV-122B, 123B)-
      -----Verify Reactor. Head Vent Block Valve (0.3)                                  (INC-250A) and Reactor Head Vent.(0.3)- (INC 253A) closed.
REFERENCE'
    . CATAWBA                            EP/1/A/5000/03 p.4               (Retype #8) 000055G010-                                ...(KA'S)
QUESTION                             4.10         (2.00).
: a. One of the requirements in EP/1/A/5000/2A1, " Nuclear Power Generation /
ATWS" is the initiation of boration of the NC system to obtain adequate
           . shutdown margin.                           What actions must the operator take to accomplish this
           !part of the procedure?                                                                              (1.5)
: 6. What are the TWO MCB actions listed in EP/1/A/5000/2A1 necessary to isolato all dilution paths.                                                                         (0.5)
I l
                                                                                                                          .I l
j

1
     'Nt__E8QGEE)URES - NORMALE_8BNQRd86x_gMEBGENGy_8ND                                                                      PAGE' 45 )
RADIOLOGICAL CONTROL
         - + ..
i
[ ANSWER ^     4.10        (2.00)-                                                                                                J 1
        'a. 1. Ensure that NVLPump 1A or 1B'is energiced,                                                                              i L
: 2. Ensure at least one NV flow path aligned to NC system.
            - 3.f0 pen'' Boric Acid-to NV. Pumps Suction Valve'(1NV-236B).
l
            . 4.1 Start 1A and.1B Boric Acid Transfer Pumps                                                                            l i
1 5.' Ensure greater than or equal to 75 gpm " Emergency.Borato Flow"'.                                                     i
: 6. Check' Pressurizer pressure less than 2335 psig.                                                                      ,
L                                                                                 (0.25 each answer) i
: b. Place NC; Makeup Control switch to stop.                                                                                   !
            -Stop. Reactor Makeup Water Pumps 1A and 1B.                          (0.25 each answer)-
IREFERENCE
       ' CATAWBA    EP/1/A/5000/2A1- p.4,5         (Retype #2)
       ;OOOO24A117        OOOO24A206       . . . ( KA ' S ) '                                                                          ;
4 1
     ; QUESTION     4.11       -(2.50)                                                                                                 !
Step 2'of' Abnormal Operating Procedure AP/1/A/5500/02, " Turbine Generator                                                   !
Trip", requires the operator to ensure the turbine has tripped by
                    ~
l observing that.all turbines stop valves are closed.                    If this response is                                    !
NOT obtained an operator is dispatched to locally trip the turbine while                                                      j
        .the' control room. operator attempts to runback the turbine.                                                                  l 1
a.' What controlfboard manipulations must the control room operator                                                    i perform to conduct the required turbine runback.                                                          (1.0)    l I
: b. IfEthe turbine cannot be tripped locally what THREE actions could then be taken or directed by the control room operators to stop the_ turbine?                                                                                     (1.5)
{
w i
i l
___:--=___________ _ _ _

     '4 __EBQGEDUBES_i_NQBM86t_8@UQBM86t_EMg8GENQY_8NQ t                                                                                                                                    PAGE 46
             ;68DIOLOGICAL_gQNT8QL E     ,
                       ~
L . ANSWER                                               4.11         (2.50)                                                                          .,
1  ,
in..    ' Simultaneously depress the "On" and " Bypass" pushbuttons on the Turbine                                                                ,
Control Panel (match CV signal with " Standby Load. Set" potentiometer and depress "ON" pushbutton)- (0,5) and rapidly unload the turbine using the; " Standby Load Set" potentiometer. '(0.5)
: b.          1. Depress'the "OFF" pushbuttons for the:" HYDR. FLUID PUMPS"(O.5).
l!                 2.                          Open CB1 and CD2 breakers in the EHC cabinet. (0.5)                                                       !
L                  3.                          Close MSIV's and'MSIV Bypass Valves (0.5)
:       REFERENCE CATAWBA                                         AP/1/A/5500/02     (Retype #7)  p.3 045050 GOO 9                                           ...(KA'S)
OUESTION                                          4.12         (2.00)
With the, plant in Mode 1 operation, a serious . fire breaks out in the Control Room.                                          State the'EIGHT .immediate operator actions required by AP/1/A/5000/17, " Loss.of Control Room," after it is determined that
        ' evacuation is required until the evacuation is announced on the communication system.
ANSWER                                             4.12         (2.00)
        '1. Unit Supervisor (Shift Supervisor) takes over OATC and sends NCO to ASP to perform enclosure 1.
: 2. Trip Reactor
: 3. Ensure' Main Turbine Tripped
: 4.    . Trip BOTH CFPTs
: 5. Trip ALL NC Pumps 16.'   Check 1 ETA'and 1ETB Energized
: 7. Ensure Letdown Orifice 1B(1NV-10A) closed 8     Ensure-ALL CRD Vent Fans Running (0.25 each answer)
REFERENCE-CATAWBA                                         AP/1/A/5500/17    p.2   (Retype #15)
        ~OOOO68G010                                             ...(KA'S)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
i

Lat__EBQgEDUBgS_ _NgBd861_GBNgBd861_gdEBGENgy_8ND                              PAGE    47
                . RADIOLOGICAL CONTROL-QUESTION      4.13         '( 3. 00) a.=     The plant is' operating at 100% power with' systems lined up f or normal operation.-The 1A NV Pump is the only charging pump in operation.
When pressurizer level begins to decrease due to apparent NC leak, what are the first TWO immediate action steps that the operator should take in accordance with AP/1/A/5500/10, " Reactor Coolant Leak". Assume pressurizer level continues to decrease slowly. (Notes there are a total of four actions required by the two steps.)                     (2.5)
: b.      State.the caution listed prior to the Immediate Action steps of AP/1/A/5500/10 concerning the use of the Centrif gal Charging Pumps.
(0.5)
ANSWER.      ~4.13         '( 3. 00 )
: a.     ' Reduce letdown flow (0.5) TO 45 gpm (0.5).
Align the CCPs to-the FWST (open the NV Pumps Suction valves from the FWST 1NV-252A and 253B) (0.5).
Close the VCT Outlet Isolation valves (1NV-188A and 189B) (0.5)
Start CCP 1B (0.5).
: b.      The. caution states that a maximum of one CCP should be operated when aligned to the VCT. (0.5)
REFERENCE CATAWBA AP/1/A/5500/10 p.2,3           (Retype #8)
OO4000G014           ...(KA'S)
QUESTION      4.14          (1.50)
In accordance with OP/0/A/6100/06, " Reactivity Balance Calculation":
: a. What is the allowable band between the Estimated Critical Rod Position (ECP) and the actual critical rod position during a reactor startup?                                        (0.25)
: b. If criticality in achieved below the ECP allowable band, but                 ,
I above the-control rod insertion 1. i mi t s , what action is required by the Operator at the Controls (OATC)?                           (0.25)
: c. If criticality is achieved below the Technical Specification               l control rod insertion limit, what action is required by the OATC?
(1.0) inn-si    i ,

l -.
4 __EBQCEDUBES_ _NQBd86t_8BNgBd862_EDEBGENgy_8ND                                                                                 PAGE 48
       , ,,88D196991986_CgNIBg6                                                                                                                            ]
i 1
ANSWER                                            4.14         (1.50)                                                                                 l
: a. PLUS or MINUS 500 pcm.                                                     (0.25)                                                              1
: b. Continue normal ops., Notify reactor engineer                                                 (0.25)
(Will also accept notify Shift Supervisor)                                                                                /
: c. Borate (0.25) at greater than or equal to 30 gpm from BATA(0.25) while withdrawing control rods to maintain criticality (0.25) until the control rods are above rod insertion limits (0.25).
REFERENCE CATAWBA                                          OP/0/A/6100/06 p.1 of 3 (Retype #11); 2 of 3 (Retype #11);
ENCL. 4.2 p.8 of 8 (Retype #11)
OO1000 GOO 1                                             OO1010A207                ...(KA'S)
QUESTION                                          .4.15         (1.50)
Explain why the Steam Tables should NOT be used to determine subcooling margin when using CATAWBA Emergency Procedures.
ANSWER                                            4.15         (1.50)
CATAWBA instrumentation has a 20 degree F (0.3) conservation factor (0.3) built into both RVLIS (0.3) and the data book curves (0.3) which would render steam table calculation inaccurate (0.3).
REFERENCE CATAWBA Handout OP-CN-HO-EP1 p.16 193OO3K124                                              ...(KA'S)
(*t*** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

     ' 4 .'        PROCEDURES - NORMALI_8BNQBMGLt_gMgBGENCy_8Np                                                                                                                                                                                                                     PAGE           49
           .     ,,B9pI96991c86_cgNIBQL L
l i
      ' QUESTION                                   4.16                                                             (2.00)
Answer the f ollowing concerning verification of valve and breaker position                                                                                                                                                                                                                     '
1 in accordance with OMP 1-5 " Independent Verification" and OMP 2-33 " Valve and Breaker Position Verification and Valve Operation".                                                                                                                                                                                                                                         :
1
: a.                    How is an independent verification performed for a NI system THROTTLED valve?                                                                                                                                                                                                                  (0.8)                {
: b.                      If an individual performing, a second independent verification discovers-a valve out of position, what are the indi viduals responsibilities?                                                                                                                                                                                                                 (0.4)
: c.                     State four (4) methods available to verify a 4.16 KV Blackout Breaker position.                                                                                                                                                                                                                 (0.8)
     --ANSWER                                      4.16                                                             (2.00)
: a.            (Since the valve is in the safety injection system it would be locked with a tamper seal.) The two individuals would both verify that the valve has.a tamper seal (0.4) and that the seal is intact (0. 4 ), DJ' }f' CAWpippa D1Mst VAnf n DiW Pf7 6 A 1l'i f f r ik f f 1 p .~ -t vs f f w w pngn 7dCZINAK (0*'O THf VfAdiff 06tfMf3 fpf Sf1DWS MME BY he JMent**. (0* V)
: b.           1. Contact the Shift Supervisor immediately and do not reposition the valve without the Shift Supervisors permission. (0.4)
: c.            1.                    Observe the mechanical open/ closed window on the breaker cubicble.
: 2.                     Observe the indicating lights on the breaker cabinet.
: 3.                     Observe the indicating lights on the breaker control switch.
: 4.                     Observation of the operating conditions (such as the amp meter (Ff Y At                            for a pump motor) or control room breaker indication.
l-        AO.2 each answer)
: 6. V541Fy' $MDft fol'Tl& /W ONMIA* C#0'h5*
REFERENCE CATAWBA                                   OMP 1-5                                            p.5;                                    OMP 1-33                                                  p.3,8                                                                                             j 194001K101                                                                  . . . (KA' S)
(*****                                CATEGORY 04 CONTINUED CN NEXT PAGE *****)
I

4.s__EBOCEDUBES_ _NOSD8L1 _8pNOSD86t_EbE8GENCY_8ND                                  PAGE    50 R
  . .. RADIOLOGICAL CONTROL QUESTION      4.17            (1.50)
State how each of the cases belcw relates to DUKE'S administrative or NRC LIMITS.
: a. A 31 year old mai r.tenance worker , with a recorded lifetime dose of 43 rem, receives a total of 480 mrem whole body exposure while repairing a contaminated pump.          Assume the job started on 07/01 and completed on 07/11 and the exposure was constant and continuous over the job duration.                                        (0.5)
: b. A 21 year old auxiliary operator, with a recorded lifetime dose of 2.3 rem, receives a single exposure doce of 16 rem while locally operating equipment to assure accident mitigation during an emergency (with the Recovery Manager's approval).                        (0.5)
: c. A visitor with an exposure class 1 receives an exposure of 1.20 rem.                                                                (0.5)
ANSWER        4.17            (1.50)
: a. The only limit in question is the 500 mrem l i mi t -f w        J n.- f l i 11 a mah which has not been exceeded.                                                   (0.5)
: b. The dose given will violate the NRC lifetime limit / proviso of 5(n-18).
Single 16 rem dose is allowed under emergency conditions.                       (0.5)
: c. A visitor with exposure class 1 is limited to 1000 mrem so 1200 rem exceeds the authorized limit.                                                   (0,5)
REFERENCE CATAWBA Handout OP-CN-HO-HP               p.12,13 194001K103         ...(KA'S)
DUESTION      4.18            (1.00)
: a. What are the THREE radiation dose l i mi t ati ons imposed on an UNRESTRICTED AREA?                                                            (0.6)
: b. What is the def i n i t i on of a RADIATION CONTROL AREA?                     (0.4)

az__EB9GE99BES_ _NQBd86,_ODNQBd862_EdEB9ENgy_GNp                                                                                                                                               PAGE               51
        .. ,!$8D196991c86_c9 NIB 96 ANSWER                                                                     4.18               (1.00)
: a.                                    Dose received in an unrestricted area would be less than 2mr/hr (0.2);-
100 mrem in 7 days (0.2); 500 mrem in 1 year (0.2).
: b.                                    Radiation Control Area is an area within the restricted area where personnel monitoring is required (Reactor and Aux buildings except for
                                      .CF and electrical equipment rooms) (O.4)og REFERENCE CATAWBA Handout                                                                      OP-CN-HO-HP p.15,16 194001K103                                                                        ...(KA'S) f                                 &% A                                                                              f   lf9*
e-~ A M w A                                                                                                               A M A #4 w -7 7                                                                                                  h a ,s,~ n m 4 M < Au M.
i 1
l l
i
                                                                                                                                                                                                                                             )
l l
I l
-         _ _ _ - _ - - _ _ _ _ _ . _ _ _ . - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . .                  m   _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ .             - - _ . _ _ - __       . _ - . _ _ _ _ _ _ . _ _ _ _ . _ _ _    _ . . - _ _ _ _ __

r
                          -                     U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR. OPERATOR LICENSE EXAMINATION FACILITY:             _CGIGWD0_1&2_____________
REACTOR TYPE:         _PWB-WEGS________________
DATE ADMINISTERED: _8pfg9fg6________________
EXAMINER:              REGION II CANDIDATE:                ,        __  _  _    _
INSIBUCIIgNS_Ig_CONDID61El                                                              /MASTEL Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets.                                        Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6)                                       hours after the examination starts.
                                                                  % OF CATEGORY                     % OF    CANDIDATE'S              CATEGORY
__MBLUE_ _IQIGL                      ___Sgg8E___              _M@6UE__   ______________gGIEGQBY_____________
_29tOQ__ _M                          ___________              ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS gg,.g f                                                                                                         >
ted4Y                                                                        PLANT SYSTEMS DESIGN, CONTROL,
_i22I2__ _@fIE@
___________              ________ 6.
AND INSTRUMENTATION 2.7 7)'                                                                     PROCEDURES - NORMAL, ABNORMAL,
_kUzZ6__ _2S:22           -
___________              ________ 7.
EMERGENCY AND RADIOLOGICAL CONTROL 28 7,S~
________ 8. ADMINISTRATIVE PROCEDURES,
  -91+IEE~_ _25 22           -
CONDITIONS, AND LIMITATIONS 41 Ef                                                                        Totals
,-liusli__                             ___________              ________%
Final Grade All work done on this examinati on is my own.                                   I have neither given           .
nor received aid.                                                                                              l i
,                                                                                                                   1 1
1 Candidate's Signature r
_ - - .          - _ --           --   - - - - -          -    -                                   J

       ;Dz_ IdEgByigE_NUQLEBB_EgyEB_ELONI_QBgBBIlgdi_ELylpS t_AND-                                                                                   '
                                                                                                                                                            .PAGE     3 1 THERMODYNAMICS                                                                                                                                             ')
x-   ,
1 l
QUESTION             5.01                                                   .( 1. 00)
SCENARID':
In' verifying primary side. natural circ conditions, step                                                                                            l 2.19.1 (Enclosure 4.2), in procedure OP/0/B/6100/13,                                                                                                 !
                        " Standby Shutdown. Facility (SSF) Operations", states:                                                                                                 !
                               '" Veri f y NC System i s subcooled by ' using Incore T/C's and.NC system pressure as read on SSF gauges                                                                                            ;
                                                                                                                                                                              ~
and comparing to steam tables...
1 NOTE.A:                                     'If.ref. junction box temp devi'ation is
                                                                             .negati ve - (-) then add the absolute value of the deviation to the T/C readout to get. actual care temperature.
L                               NOTE;B:                                     .If ref.' junction box temp deviation is positive (+) then subtract the.value of the deviation to the T/C readout to get actual core temperature."
The f ollowing plant parameters are noted at the SSF:-
Incore T/C's readout .                                                         =
* 600 degrees F (TE-36, 48, 50, 52, 64)                                                                                                                     ,
1875 PSIG NC System Pressure                                                             =
I (NCP5121)
NC System P2R Level                                                            =
* 35 percent (NCP5154)
Reference Junction                                                             =           *
(-)   25 degrees F Box #2 Temperature T-Cold is near saturation temp for S/G pressure and pressure is being controlled by S/G cafeties.
Using the.above-(previous) parameters and standard steam.
         ' tables, SELECT the most accurate description of conditions that would be'present in'the NC system
                   'a)         -Saturated (slightly "superheated") core conditions exist in the NC - Possible bubble formation in vessel - natural circulation conditions NOT met.
b)      Subcooled core condition MAY be present in the NC
                                - Subcooling Margin (SCM) is less than 10 degrees F - natural circulations conditions questionable.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
1-___________                                                          _ _ _ _ _ _ _ _ _ _ _ _ _   _ _ _ _ _     _._               ___     ._       __.
_j

r: ;
4Dz__IBEORY OF= NUCLEAR POWER EL8NI_QEgB8IlgNz_ELUIDSt _8ND'                                                                                                                                                                                    PAGE 4 LIBEBd9DYN8 DIGS 7?                 -
I'      [g c)     Subcool'ed coreLconditions exist in the=NC -
n                           SCM is" greater.than-10. degrees F.but.less than.50
    ,                                      degrees.F - natural; circulation conditions met.
                                    .ch     Subcooled core conditions exist in the NC -
                                           .SCM is. greater than 50 degrees F - natural circulation conditions met.
ANSWER                           5.01                                                                                                                 (1.00) e b)~                     (1.0)
The following calculation IS NOT required:
L Tsat for.1875-PSIG (*1890 PSIA) = *627.9 degrees F Incore T/C's. Readout'                                                                                                                                                                      =   600.0 degrees F LJunction1 Box Temp Deviat2on                                                                                                                                                               ' = . 25.0 degreen F Subcooling Margin = Tsat m CIncore T/C                                                                                                                                                               (+) ' Deviation]
           . NOTE:                      If ref. junction box temp deviation is negative                                                                                                                                                       (-)
then absolute value'of the deviation is ADDED.to the T/C readout to get actual 1 core temperature.
                                                                                                                                                                                                     ~
Subcooling Margin = '627.9 - 625.0 = '2.9 degrees F REFERENCE T&Q'CO-ROOO4,rElement #6E; T&O' CD--ROOS 2, ' Element #2; Catawba LP OP-CN-HO-HT; Pgs 7-9; LPSD Objective __; Catawba LP OP-CN-HD-AD;.Pgs 19-21 AND OP/0/A/6100/13; Enclosure 4.1 KAIR 3.3/3.4 193OO3K125                                                                          ...(KA'S)
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
I
            .mi___i__                        _ _ . _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ . _ . _ _ . _ _ _                      _   - . _ _ _ _ _ _     ._ _

dz__IHgDRY~OF NUCLEAB_EgWEB_E6eMI_gEEB9IlgN          z _ELulpS _eND                                     PAGE 5 THERMODYNAMICS u      ..
L              .
QUESTION       '5.02           (1.00) l,it-When synchronizing the generator to the grid, OP/1/B/63OO/01 L'      .", Turbine Generator Startup" directs the operator to regulate turbine speediby slowly rotating the synchroscope in the
        . f ast (clockwise) direction.                                                                                 ,
        "From the fdllowing, CHOOSE the correct parameter that the synchroscope:is. indicating:
a)     Current and voltage difference b)     Voltage'and frequency difference c)     Phase and resistance difference d)     Frequency and phase difference                                                                 j e)     Resistance and current difference LANSWER'          5.02           (1.00)                                                                        ..
d)      (1'0)
REFERENCE
        ;T&Q CD-RO170 Series; Catawba LP OP-CN-HO-DG3; LPSO Objective 8; Pg 10; Catawba LP OP-CNS-HO-EGB; LPSO Objective 2e; Pgs 9-10; Ops Procedure OP/1/B/63OO/01, " Turbine-Generator l
Startup" KAIR 2.8/2.9 062OOOA403           . . . OGY S )
(***** CATEGORY 05 CONTINL'ED ON NEXT PACE   *****)
I

l Dz__IU598Y_9E_NWCLg88_EgWgB_ELONI_gEgBSIIQN                                                                                                                                                  x _ELylpst_GND-               PAGE    6 F
           . THERMODYNAMICS is      ..
QUESTION- 5.03                                                          (1.00)
L      L Which ONE (1) of the'following statements is CORRECT concerning the. paralleling of electrical systems?
a)     If resistances are not matched when the
[
synchronizing switch is closed, heavy currents l                              will flow - this tends to speed up the incoming machine to synchronous speed.
[
b)     If' voltages are not matched when the synchronizing switch is closed,'there will be VAR flow from the lower voltage' source to the higher one.
                       .c)     If.the incomingfmachine is in phaso but slightly faster.than synchronous speed when paralleled, the system will tend to speed up to synchronous speed.
Ld)      If the incoming machine is at. synchronous speed but out of phase with the running bus when.the breaker is closed, heavy currents will flow to either accelerate or retard the incoming machine.
ANSWER                 5.03                                             (1.00) d)               (1.0)
REFERENCE T&Q CO-RO170 Series;.LP OP-CN-HO-DG3; LPSD Objective 8 KAIR 2.8/3.2'
       '062000A215                                   ...(KA'S) l
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

C'
                   .5.. THEORY"OF NUCLEAR POWER PLANT OPERATION2_FLUIDSz_AND_.                                                                                                                                        PAGE 7
                             . THERMODYNAMICS.
F LOUESTION' 5.04                                                                         (1.50)
                     -Choose responses which correctly complete the.following:
                     'a)          'One way in'which'an operator can minimize the-possibility of creating a " water hammer" is to start' a pump with it's dischargo valve (OPEN, CLOSE D ) '.
b)     '
                                  .By controlling (PUMP. SPEED, DISCH. VALVE POSITION) 'we control' volumetric flow rate out of a posit.ive
                                  . displacement pump.
                      .c ) :       Ideally,.when TWOL(2) pumps are placed in a-(PARALLEL, SERIES) configuration, maximum flow capacity produced is.no' greater than the capacity of DNE (1) pump.
ANSWER-                                     5.04                                      ( 1. 50 )'
                     -a)           CLOSED.                                                                (0.5) b)'         PUMP SPEED                                                             (0.5) c)-         SERIES                                                                 (0.5)
                      . REFERENCE Catawba LP OP-CN-HO-FF; Pgs 11, 18, and 19 AND Catawba TDrawing CN-THF-FF-9
                     'KAIR 3.3/3.4, 2.2/2.3 3.1/3.3 193OO6K110                                                                    193OO6K113                                             193OO6K115                                    ...(KA'S)
\'
(***** CATEGORY 05 CCNTINUED ON NEXT PAGE *****)
L

i 191__IHEQBy_QE_NUC6g88_EgWEB_E68NI_gEEBBIlgN1 _ELQ1Dgt_8ND                                                                             PAGE 8
=..                                        THERMODYNAMICS I:
      < QUESTION' 5.05                                              (2.50)
SCENARIO:
l                                                 The plantLis operating'.at 30 percent power, turbine in AUTO (IMP IN), when loop number ONE -(1) reactor coolant pump trips.
            ; Assuming no reactor trip, no. operator action and' rod control-in' MANUAL, indicate whether the'following parameters will be
        -HIGHER, LOWER, or the SAME at the end of the transient compared to their initial values.
         .a)                                     ' Number THREE (3) NC loop flow ti)                               Number TWO (2) S/G steam pressure
         ''c )                                    Number TWO. (2) NC'T-HOT d)                               . Number ONE (1)''NC T-COLD e)-                                Nuclear Power-ANSWER-                                        '5.05         (2.50)
Each' worth 0.5 points a)                                 HIGHER (Less resistance-to flow'>> Other NCPs speed up) b)-                                LOWER (Higher Steam Flow'>> P steam decreasesO c)                                 HIGHER (Less total flow across core ->> delta T increases, .T-HOT increase with rods in manual) d)-                                LOWER.  (As  above,-delta T increases, T-COLD decreases) e)                                 SAME    (Primary Power n secondary load)
          ' REFERENCE Catawba LP OP-CN-HO-FF; Pg 15; LPSO Objective Oa AND General
          -Physics HT&FF Part 8, Chapter 1, Pgs 129-162                                                                                                   )
KAIR 3.4/3.7                                     3.7/4.0 3.5/3.0 OO2OOOA105                                     OO3 COOK 301    OO3OOOK302                                           ...(KA'S)
I
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

m              ..
      '5.         THEORY OF NUGLg88_EgWER_ELANT_gEgR8TIQN           i _E6ulpg1_eND PAGE 9
                !THERMODYNSMIg@.
: a.          .,
o QUESTION' 5.06                    (2.00)
        'If steam goes through'a throttling process, indicate.whether
         'the.following, parameters will' INCREASE, DECREASE or REMAIN
        -THE SAME.
a)          Prossure g         b)         .Enthalpy
:c)          Temperature d).        -Entropy ANSWER.           5.06-          (2.00).
a ).        DECREASE                 ' (0. 5)
         !b)          REMAIN THE SAME           (0.5) c)          DECREASE:                 (0.5)
         'd)          INCREASE                  (0.5)
REFERENCE Catawba LP OP-CN-HO-THF; Pgs 18-.19; 'LPSO Objective 6e KAIR. 2.6/3.0              2.8/3.4
         .010000K502.               193OO4K115          ...(KA'S) s QUESTION           5.07-         (1.50)
        .TRUE or FALSE
        'a)           During reactor startup, " criticality" occurs when the-fission chain reaction becomes self-sustaining and the neutron level is independent .cf source neutrons.
b)          The reactor is made slightly supercritical during sta-tup.because this allows for positive indication of
                     'the reactor's status.
L       .c)           A reactor is critical et 10 E'-08 amps in the Intermediate Range;     If the neutrcn source is removed, the neutron
                     . level would drop to a-lower value and then remain constant..
l l'

y  ,f                  4 151. THEORY QE_NyGLEBR_' POWER' PLANT OPERATION                                       t _ELUIRet_8ND      PAGE 10 ISEBdQDXN8 digs
      .:          c..
     .c               :
ANSWER.                  : 5. 07'                       (1. 5C )
a) .       "TRUE                    (0.5) ib)            :TRUE-                   ( 0. 5) c)J          TRUE                   (0.5)
   +
         ' REFERENCE T&Q CO-RO120, Elements #1 & #5'AND Catawba LP DP-CN-HD-SCM; Pg 17; LPSO. Objective 11 cKAIR 3.3/3.4
          '192OO8K1101                           ...-(KA'S)
( 1,, 50) 4 LQUESTION. 5.08 1TRUE or FALSE" a')         :The removal rate ofgXe-l'35 is dependent on TWO (2)
Lfactors: .the decay rate of I-135 and the burnup rate of Xe-135.-
b) .       . Xenon equilibrium.is achieved when the removal rate is equal to the. production rate and xenon concentration becomes constant with. time.
c)           The' equilibrium concentration of xenon, and therefore
                          ~its reactivity, varies linearly with flux                               - -(power
                        ' level).
ANSWER.                         5.08                    (1.50)
:a)           FALSE                  (0.5) b)           TRUE.                  (0.5)
:c)            FALSE                  (0.5)
REFERENCE Catawba LP-.OP-CN-HO-RP; Pgs 9 and 1(t; LPG 0 Objectives 7 & D
                                                                                                                         .l
[ , Glasstone5.90 through                  &-Seconske; 5.9d; .Lamar"Naclear      sh ; " Nuc Reactor  Enginscring":
l ear Reacteer           Parts Theory"; Pgn l~           469'through 474 l
KAIRo3.0/3.1
!        fi92006K102                             ...(KA'S)
I
(***At CAYEGOR$ 05 CONT 7NUED ON NEXT PAGE *****)
L___________________

i c5i_lIBE98Y_9EiN996E88_E9 WEB _E68NI_9EEB8I19Nt_ELUIDSt_8Np1                    PAGE   11 LISEBd99YN8d195 p_      .
1 1    ;QUESTIONi 5.09                         (1.00) .                                            ,
I nTheLfollowing~ statement appears in Technical Speci f i cati on                               {
i         -Limiting ConditionLFor-Operation (LCO) 3.2.5:                                                 !
l
                         <"The following DNB related parameters shall be                                 !
maintained within the limits shown on Tablo 3.2-1,                            l
                            'DNB Parameters's-                                                           !
: a. Reactor Coolant-System Tavg, and                              -j i
: b. Pressurizer' Pressure"                                          l TRUE or FALSE:                                                                                .
k a ')           By observing these limits, Tavg and P2R Pressure-is                            j maintained within the NORMAL steady state envelope of                          l operation assumed in the. transient & accident analysis.                        j I
b)             For transients analyzed, these limits were ALSO'shown                          I to'bo analytically adequate in maintaining the design                          l limits associated with DNBR.                                                   !
l i
                                                                                                       'l 1
MANSWER                   5.09         . ( 1.~ 00 )                                              l a)             TRl * '        (0.5)                                                           {
          'b)             Tr,ut ;        (o,5)                                                           {
l RdFERENC
          .T&Q CO-R,026,-Element #4; Catawba LP DP-CN-CTH-CTH; Pg 15,                                    1
          .LPSO Objectives 8,.9, 10 & 19; Technical Specification LCD &                                  j Bases 3.' t.5 AND Catawba LP OP-CN-H7-HT; Pgs 10-11                                           i KAIR 3 1/3.5                                                                                  j 193OO9K105                    ...(KA'S)                                                       :
t i
i j
1 1
I I
e          I
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)                  l ll
_-----J_-_-__________.____            _ _ _                                                i

                               >n PAGE '12 -
W Ul_ THEORv'OE_ NUCLE 88_EQUEB_E68NI_QEEB8IJONx_ELQ1D@t_8ND
         ~
LItEBd99YNBd1GS -
           .t;               :.
:; .. t                       ..
QUESTION                  5.10-                  . ( 1. 50)
               - T'HREE N.3 ) percent..of the tubes in the                               "A" S/G are plugged.
:n fall.' tubes in'the                                  "B",       "C"   &   "D" S/G's are operable.
TRUE~or FALSE-Due; to the reduction in' the number of tubes available in the p7-             .nno gjgg
               'a)                 The total' heat' transfer RATE of the "A" S/G will-be
                                  'less than that of the "B", "C" or "D" S/G's.
b ') '            . Total-plant power output (MW)'is REDUCED because of the "Ad 3/G output pressure reduction, dT increase, and the sub se querc. offects to Psat vercus Tsat.
       ,        c)-          '
The Heat-Transfer Coefficient ("U") will increase in the "A" S/G and decrease in the other S/G's.
ANSWER                   .5.10'                   ( 1'. 50 )
a)                FALSE              '( 0. 5) b)'               FALSE              -(0,5) c)                FALSE               (0,5)
REFERENCE
               . Catawba LP OP-CN-HO-HT; Pgs 2-4; Catawba. Drawing CN-THF-HT-2
               -KAIR 4.1/4.2 002000K111                           ...(KA'S)
I
(*****     CATEGORY 05 CONTINUED ON NEXT PAGE                   *****)
1.
l

{Di_JIBEQBY_QE_Nhg6E88_EQWEB_E68dligEEBBIIQN,_E691QQ1_GND                                                                                        PAGE 13
)
o             THERMODYNAMICS
, r.:              .
TOUESTION'.5.11-                                     (1.50)
TRUE1or FALSE a)        Since pressure stresses are higher on'the NC vessel outer wall during cooldown, cocidown restrictions'are more. limiting than~the heatup restrictions, f
ib)'       Due to the greater risk of brittle fracture, rather than cyclic fatigue, PZR'" tech spec" heatup/cooldown
                       , limits are more restrictive than NC vessel limitations.
      .       c):      The maximum limit of DNE.(1)'NV pump operable when NC                  .
temperature is below 285 degrees F assures that a mass addition pressure transient can be mitigated by operation of a single code safety.
ANSWER               5.11                          (1.50) a)        FALSE                     (0,5)
            , b)'       FALSE                     (0.5) c)        FALSE-                    (0,5)
REFERENCE T & D . C O - R O'1 3 0 , Element #1; ' Catawba LP OP-CN-HO-PTS; LPSO Objectives 3, 5, 9& 13; Pgs 11-13;' Catawba Technical Specification 3/4.4.9 LCO and Bases; Catawba Technical Specification 3/4.1.2 LCO and Bases.
KAIR 2.8/3.2 3.3/3.7 193010K101-                        193010K104                             ...(!A'S)K
(*****           CATEGORY 05 CONTINUED ON NEXT PAGE *****)
r.
-_-----_i_--_-______--_-______-.-.- - - - . - _ _ - _ _ _ - - - _ - _ . _ . - _ _ . _ _ - - - _ - _ - _ . _ _ _ _ _ - - _ - _ _ _ _ _ _ - _ - - - - _ _ - _         _ _ _ - _ _ -

ll
                   .gz__THEQBy OF NUCLEAR-POWER-PLANT OPERATIONi_ FLUID @z_8Np;                                                                                          PAGE' 14
                           -IbEBdQDXN8d1CS
:..            o;
: a.            *
  ~
1
                               ,                                                                                                                                                          l
             +  iOUESTION'                          5.12'        (2.00)                                                                                                                   l l
Forfthe following FILL:IN THE BLANK questions'use either
, t              ,
F.1= " Heat-Flux" Hot                          OR. F                   = "Enthalpy Rise",                                                                         j
                       .O           Channel. Factor                        Delta H               Hot Channel Factor q
a):        -The _______' hot channel. factor:is based upon maintaining'the DNBR'at values consistent with CNS accident analysis.
1-.
I
                    ;b),          The _______ hot channel factor.uses a "subfactor" which ratios peak-to-average' linear power (kw/ft). densities found on a horizontal. plane in an area of the core which-has highest local kW/ft density.
c)          The _______ hot channel' factor uses a "subfactor" which divides the. average kW/f t density f ound on a horizontal plane in an. area of the core with the max. local kw/ft                                                                                               q density by the avg kw/ft density for the entire core.                                                                                                   l 4
                    'd)-         LThe _______ hot' channel factor,.by definition, is equal                                                                                              1 to the." hot" rod' power divided by the " avg" rod power.
JANSWER                             5.12         (2.00) i a)-         F                        OR  "Enthalpy Rise" Hot Channel Factor                                                                  (0.5)
Delta H b)           F                        OR   " Heat Flux" Hot Channel Factor                                                                    (0.5)                I O
c)          F                        OR   " Heat Flux" Hot Channel Factor                                                                    (0.5) l Q
                     .d )         F                        OR  "Enthalpy Rise" Hot Channel' Factor.                                                                (0.5)                f Delta H REFERENCE T0Q CD-ROO26, Elements #1 & #2; Catawba LP OP-CN-HO-HCF; Pgs 2'through 7; LPSD Objectives 1 and 2 AND Westinghouse;
                      " Nuclear Power Distribution & Core Control" Material KAIR 2.9/3.1 192OO5K112                           ...(KA'S)
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
I

  'Dz__IBEgBy_QE_Nyg6E88_EgMEB_EL6NI_QEEBOIlgN1 _E691gSt_8ND                                                                                          PAGE 15 IUEBdQQyN$ digs QUESTION- 5.13                                         (2.00)
LIST the FIVE (5) indications of natural circulation IAW Enclosure ONE (1), EP/1/A/5000/1A1, " Natural Circulation Cooldown" procedure.
  . ANSWER                         5.13                    ( 2. 00) a)                        NC Subcooling greater than ZERO (0) degrees F                                                                    (0.4) b)                        NC T-hot wide range - steady or decreasing                                                                       (0.4) c)                        Core e>:i t thermocouple - steady or decreasing                                                                  (0.4) d)                        S/G pressure constant or decreasing with T-hot                                                                   (0.4) e)                        NC T-cc,1 d (Wide Range) near saturation temperature for S/G pressures.                                                                                               (0.4) iREFERENCE T&Q CD-ROOO4, Element (16; Catawba LP OP-CN-HO-HT; Pg 7; LPSO Objective __; Catawba LP OP-CN-HO-EP1; Pg 19, LPSO Objective SC AND EP/1/A/5000/1A1 Procedure and Associated Enclosure #1 VAIR 4.2/4.2 3.9/4.1 193OOOK123                             193OOSK122                               ...(KA'S)
DUESTION                       5.14                     (1.00)
Using                      the graph below, PLOT the " Xenon Concentration versus Time"                      curve that is associated with the given " Percent Full Power                      versus Time" curve - i.e.; Show how Xe concentration would                      respond to the given power changes.
                                        -       i             l 1 1 II I I I j                                                             i i y  - .o o s.  -l                                                                 -
2
                                        ~'
1 bo%
                                                                                                                                         /
                                        $ - os l    e     er w   ,e               w-                         eep.   -m   a      uteme >gme es i                                                      i 7 7                                                           l   l                           f
                                        -                           i                                                i 5                           l                    l                           i eo I A            o       .o   to          so             .o           so        .o                ro
                                        $            I        l     l         I~             ""5 l         l                 {   l l1                        i

    ?4 5d;_IBE98Y_9E_NUGLEBB_EQWEB_EL8NI_0EEB8Il9N&_ELUIDS t_GUQ                                                                                                                           PAGE' 16 THERMODYNAMICS
  'v               .,
       ' ANSWER                         ; 5.1'4                                                  (1.00)
Place CNS LP CN-RT-RP-TP-13-drawing HERE.as the " master".
Look for-the followings-f:        .a)           . Correct _ representation of Xe Conc change in response to ZERO (0) percent to 100 percent power change.                                                                        (0.20)
         ' b);           Correct representation ' of' Xe Conc change in response to 100 percent to ZERO (0) percent power " trip".                                                                       (0.20)
         'c)             Correct representation of Xe Conc change in response to ZERO (O). percent to 50 percent power change.                                                                        (0.20)
           'd );         Correct representation of Xe Conc change in response'to
                        -50 percent to 100 percent power change.                                                                              (0.20)
         "e)             Correct representation of Xe Conc achieving equilibrium conditions while at 100 percent power.                                                                               (0.20)
         -REFERENCE
           . Catawba LP OP-CN-HO-RP; Pgs 8 and 9; LPSO Objectives 7 and 8; CNS Trg Drawing CN-RT-RP-TP-13; Glasstone & Sesonske;
              " Nuclear Reactor Engineering"; Parts 5.90 through 5.101 Lamarsh; " Nuclear. Reactor Theory"; Pgu 469 through 474 KAIR 3.1/3.1 192OO6K111                         ...(KA'S)
       ' QUESTION                         5.15                                               .(1.00)
Using-the single " Pump Head (Hd) Versus Flow Rate (V)" graph
                                                                                                                   ~
provided, SKETCH / DRAW:
a)           The THREE (3) Emergency Core Cooling System (ECCG) pump curves SHOWING relative position to one another.
b)           TWO (2) " system characteristic curves" depicting:
1)- The " system curve" associated with initial reactor coolant system (NC) pressure AND;
: 2) ONE (1) .other " system curve" which would be representative of system characteristics during a major reactor coolant system (NC) LOCA.
                -_                  _ - -       _ - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ . - - _ - _ - - _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ -   _      _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ = _ _ _ - _ _

i Qi__ THEORY QE_NVQLE68_EQUEB_ELONI_QEEBQIlQN,._ELylph_GNQ                                           PAGE' 17 Se It!EBdOQYN8t} LGS
  "        . ANSWER.                              5.15         (1.00)
                                         - USE ATTACHED FIGURE INLGRADING THE QUESTION -
             "LOOK FOR THE FOLLOWING:
              - a )'                 , Correct placement / labeling of NV pump curve             (0.2) c)                       Correct placement / labeling of NI pump curve.          (0.2) d)                       Correct placement / labeling of ND pump curve. .        (0.2) e)                       Correct, placement / labeling of Init Sys curve.        (0.2) f)                   ' Correct placement / labeling of-curva depicting
                                    . system pressure reduction due to LOCA.                     (0.2)
               . REFERENCE Catawba LP OP-CN-HO-FF; Pg 17 AND Catawba Drawing-
              ;CN-THF-FF                 KAIR" 2.8/3.1                            3.5/3.9.
006000K506                              '006020K601       ....(KA'S)
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

{                 i Un s
{
D boDb m                                                         .
                                                    '                                 7 8
1 g
2
                                                              /                                     ,
l S
l
                                                                    -   O           "j         r.
                                                 -                      8             3        ~-  uo 1
e
                                                              .A        O 7
P T
P R
T a
o C
r A
1 s
                                                                                                    ~,
R-         a S
N          w C         -
0           "      ,    -
_                    6
                                                                                           ,   a 0
5
        '                                                                   S I                                                   0   RI 4 H I
I                                                   0 3
s                  -
I                                                                 s e
I 0
2 I
R S OE 0            F G 1                   N            -
SA TH NC                 -
EI SR NE O-            AW HO
                           %      */.   */.                                           TP 0      O     0                                              N
                    '          I.
                                  $-  I O S    U 0
1 U' E O   I XR e                      -
* V A
5 iO s a- j2u. $                         o8o zga*
p                                                                   t i,             l.                                                                                            -

___ , , . . - - - - ~ -
i
!.YNQ                                                                                                                                         ia    ,
i i
k
                                                                                                                                             ~        ai h                                                                                                    I
                                                                                                                                                      ,l, 2d U
* M6l4 'd w$                                                                                          k,      e.
Gwo       th                                        -
                                                                                                      'h                                       "
s m            se
                                                   #$ >d           O-E i
3 o
                                                   $3              M                                                                                  I ad                                                                                        o at d                                                                                           i    &'
w a
                                                     \          s 8
2 w       %                   %
                                                 $          \                  %
M             g%                 \
J                %                  \
5 gl
                                                                    \                  %
g\                 \                \
                                                 $                                         \                                                      $
s%              \g                 \                                                    2 g                g             o
                                                %g              g                \                                                                S s              '                               \               '>
s s
                                                                   \
                                                                     \\            N     s s.
s n
                                                            \             \
                                                                                          \              \
                                                              \            \               \
                                                               \                            g
                                                                             \
                                                                \                            g
                                                                              \
                                                                 \                                         g
                                                                               \
                                                                  \                                         g z
                                                                                 \               g           \
                                                                                  \ z  -
                                                                                                  \           \
                                                                     \             \              g            g I                            g            1 g            h                t           i e                                                               ,
T.                                                              9 w
O
                                                                                                                                                 ;d

I Dz__IBEDBY_DE_NWGLEBB_E9 WEB _EL8NI_9EEBBI19Ni_ELUIDEx_8NQ                                       PAGE' 10 ISEBd9DYN6 digs
_              *----+-,4.mn.,               n l
l QUESTION                5.16                           (1.00) l-                     SCENARIO:
The on-shift RO inadvertently placed a "not fully' saturated" mixed-bed demin in service.                                  The RO was then told that'the demin had not been. properly saturated and in &t rn, took.it out of service.
As the shift. supervisor, you notice that over the 1ast 30 minutes, reactor power has increased from a previous
                               ' steady-state power level of *85 percent to the present steady-state power-level of '91 percent.
Given the following conditions AND using Boron Control Data
                      .Hrndout information, CALCULATE the amount of boron (in ppm) removed:
                               - Rod control'"is in manual with no rod motion L                  - Letdown flow is *70 gal / min
                               - Initial NC boron concentration was '900 ppm (30
                               - . g.g- -                          -
l i
                               - No , load changes were perf ormed over the l ast 30 minutes
                     'SHOW ALL APPLICABLE CALCULATIONS - NOTE ALL ASSUMPTIONS
                                                                                       .see
* euw k',
Y
      !                                                    ($$$$$ CATEGORY 05 CONTINUED ON NEXT PAGE *****)                      .
   . \-
6                          -
m . .r                                                                               !
     @'                                .d       ;'               '
d-4
                                    , $df,.y' . 8
[ . .t f ' ' 4 ;> .
e
                                                                                                                                   ]

               ':n                                                                                                                         ..
4 5 '' 1THggRY-OF' NUCLEAR POWER PLANT OPERATION
           .                                                               z _FL.Ulpg3_8ND.                                          PAGE 19
                !IBEBd9DYNGd1GS J:
                 ..?
l ;' .
ANSWER'          15.16         (1.00)
[i       ,Diff: Boron' Worth-        =  *(-)10.25 pcm/ ppm (0.25)
Avg. Power 1 Defect         Avg between- 1000 & 800 ppm power defects
          '(at '90: percent from data) multiplied by a SIX (6) percent
: power change = '99.36 pcm                                                                                          (0.5)
         ;99.36'pcm
          '---------              =-    '9 69 ppm removed                                                                     (0.25) f:     10'.25 pcm/ppro
         ' NOTES: " Defect".between 95.88 - 102.96 pcm is acceptable
                        " Answer" betwoon.         9.35_- 10.05 ppm         is acceptable Any calculation " error" 'to be carried forward
: l.         REFERENCE
         'T&Q CD-RO150,l Element #2;. Catawba LP OP-CN-HO-RP; Pgs 6 & 7; LPSD Objective 4 AND OP/1/A/6700/01 Data Tables 6.2.4 & 6.4 l          KAIR 3.8/3.9 192OO8K120             ...(KA'S)
I.
1:
                                                                                                                                                )
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

        <Di__IdEgBy_QE_UUg6588_EQNEB_E68NI_gEEBSIlgNi_E6UIDS2_8ND:                                                                                 PAGE     20' LIUSBd9D%BBd1GE'
     ,4
               'd '
$c
         'QUESTIONL 5.17                                  ( 1. 50)'
iThe[following-data was obtained from Power Range drawer                                                                           "B":
NI-41                              NI-42  NI-43                              NI-44 Upper Detector,.1152V                                                    .1060V       OV                            .1012V Lower Detec' tor .1361V                                                  .1097V'      OV                            .1035V 1 NOTE.#1:                      Power range, detector NI-43 has been properly taken'out'of service due to inst malfunction.
          ;Using the above' data AND. Attachments 5-1, 5-2, 5-3 and 5-4, CALCULATE then SELECT, from-the'following choices, the most cli'miting' Ouadrant Power Tilt Ratio (or response).
SHOW ANY-REQUIRED CALCULATIONS - NOTE ALL ASSUMPTIONS a)             Between 0.900 and 1.010 b)              Between 1.010.and 1.050
                    'c)-             Between 1.050'and 1.100 d)         .Between 1.100 and 1.150 e)              QPTR cannot be determined due to instrument DOS ANSWER              5.17                         (1.50)
Attachments' properly completed (See " Key")                                                                                     (1.0)
            "d" given as correct answer                                                                                                      (0.5)
REFERENCE.
T&O CD-ROO26, Element #3; T&O CD-ROO99, Element #2; Catawba LP OP-CN-HO-PD; Pgs 10 and 11; LPSO Objectives 2 and 4; Technical Specification Definition 1.24 & LCO 3.2.4 AND PT/1/A/4600/08B " Manual Cal of Ouad Tilt & Delta Flux"                                                                                             l KAIR 2,9/3.3 192OO5K113                               ...(KA'S)
                                                  -(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
j .-

777:)C t-f nWi/ T~ f- I PT/1/A/4600/08B Page 1 of 2
   .,             ,,                                                                        Retype    #2 ENCLOSURE 13.3 QUADRANT TILT CALCULATIONS h.itial/Date
                              /        13.3.1     Transcribe voltage readings                               into Column A of table below.
                              /        13.3.2     Multiply each voltage in Column A by 1000 to obtain current in pA.
Record results in Column B.
                              /        13.3.3     Record the calibration current for each detector channel (in pA) in Column C. These currents are listed in Table 2.2 of the Unit One Data Book (OP/1/A/6700/01).
                              /        13.3.4     Divide each channel's measured current listed in Column B by its corresponding calibration current in Column C. Record         ,
results (relative flux) in Column D.
I       A      l        B      I      C       l       D        l Channel      l Meas. Voltage IMeas. Current l Cal. Current (Relative Flux   l     ;
i N41A (upper) l Vl           pA   l         pA 1                  l     !
I                l              l               !              l                I l N418 (lower) l              Vl           pA   l         pA l                  l     ,
I               l               l               1              l                l     !
l N42A (upper) l              Vl           pA   l         pA I                  I l               l               l               l              l                I l N42B (lower) l              Vl           pA   I         pA l                  I     .
l               l               l               l              l                l     !
I N43A (upper) l              Vl           pA   l         pA l                  l     j l               i               I               I              I                I l N43B (lower) l              Vl           pA   l         pA l                  l l               l               l               t              l                l l N44A (upper) i              VI           pA   l         pA I                  l l               l               l               1              1                I l N44B (lower) l              VI           pA   I         pA I                  1 I               I               I               I              I                I
                              /        13.3.5    Complete attached page to calculate quadrant tilt.
I' l-                                                                 .
l Caeshen fM

         -h77~/9C/NY){r/T" F L                                                                                                                                                                                                                                 PT/1/A/4600/08B
     ~     ,
Page 2 of 2-
      .-     .                                                                                                                                                                                                                                                 Retype                              #2 ENCLOSLTI 13.3.
QUADRANT TILT CALCULATIONS o
Quadrant Power Tilt Calculation:
Each upper or lower relative flux (RF) is divir'ed by the upper or lower average relative flux (RFA or RFB).
RFA =           (RF(N-41A) + PJ(F-42A) + RF(N-43A) + RF(N-44A)] + N
                        =         1                                                        +                                                                                      +                                                                     +                                             =
                                                                                                                                                                                                                                                                 ]+.
RFB '=          [RF(N-41B) + RF(N-42B) + RF(N-43B) + RF(N-44B)] + N
                        =                                                                 +                                                                                       +                                                                     +                                             =
l                                                                                                                                                                                                                            ,
                                                                                                                                                                                                                                                                 ] 1-Where N = # of operable power range detectors NOTE:               N/A tilt if detector is inoperable.
TILT (N-41A)              =                                                      ( -41A) ,
RFA E                                            2A) ,
TILT (N-42A)              =
RFA TILT (N-43A)              =                                                      ( -43A) ,
RFA TILT (N-44A)              =                                     E(N-44A) ,
RFA TILT (N-41B)              =                                                      (N-41B) ,
RFB TILT (N-42B)              =                                                      ( -42B) ,
RFB TILT (N-438)              =                                                      (N-43B) ,
RFB TILT (N-44B)              =                                     M(N-44B) =
RFB Enclosure Completed By                                                                                                                                                                                                                  Date Calculations Verified By                                                                                                                                                                                                                Date _
-..            __           _ _ _     . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                                                 a

                  )TTo9CHMf//F l'3
        ~
1 SOURCE                      FT/1/A/4600/05F              j PREPARED BY M.W. Hwes _                                   l EFFECTIVE DATE _1/4/88                                  J Page 1 of 2 OP/1/A/6700/01 1
                                       .       UNIT ONE DATA BOOK                                                                           f TABLE 2.2 EXCORE DETECTOR DATA 4
FULL POWER CURRENTS DETECTOR    UPPER (microAMP)      LOWER (microAMP)                                              M FACTOR N-41~
297.8                             307.8                                               1.491     .
N-42            286.2                             301.6                                               1.468 N-43            273.8                             292.2                                               1.471 N-44            237.8                             267.3                                               1.418 NOTE: THIS FORM IS TO BE USED TO RECORD THE MOST CURRENT TEST DATA i
i l
1 cadion 5.0             _ _ _ _ _ _ _ _   _   _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ -

{                             8 r 7 F") C H n g t . u ' 7 " $ - y L
c l
SOURCE PT/1/A/4150/21 PREPARED BY G.A. HARBIN EFFECTIVE DATE 12-31-87 Page 2 of 2-l                                                                   OP/1/A/6700/01                                                        ,
                                                         -        UNIT ONE DATA BOOK TABLE 2.2                   '
EXCORE DETECTOR DATA DETECTOR          25% F.P. (microAmp)
N-35                  104.3 N-36                  102.8 DETECTOR       HIGH TRIP SETPOINT (%F.P.)
N-41                     109 N-42                     109 N-43                     109 N-44                     109 NOTE: THIS FORM IS TO BE USED TO RECORD THE MOST CURRENT TEST DATA.
NOTE: WHEN REQUIRED BY ACTION STATEMENTS IN TECH SPEC LCO'S 3.2.1, 3.2.2, 3.2.3 OR 3.2.4 HIGH TRIP SETPOINTS FOR N-41 THROUGH N-44 SHOULD BE ADJUSTED TO VALUES DOCUMENTED IN THE TECHNICAL SPECIFICATION ACTION ITEM LOGBOOK.                                                                                     I we
- - - - - - - . _ . . _ _ _                             $actiion 5 0

7/G[ tffy1(A.l l           (~ l
[J/ <D"t/      b7         PT/1/A/4600/08B y
                            %9     '
Paga 1 of 2 Re t ype     #2 ENCLOSURE 13.3 QUADRANT TILT CALCULATIONS Initial /Date
                         /       13.3.1   Transcribe voltage readings                                        into Column A of table below.
                         /       13.3.2    Multiply each voltage in Column A by 1000 to obtain current in pA.
Record results in Column B.
                         /       13.3.3    Record the calibration current for isQ detector channel (in pA) in Column C. These et.rrents are listed in Table 2.2 of the Un2t One Data Book (OP/1/A/6700/01).
                         /       13.3.4    Divide each channel's measured current listed in Column B by its corresponding calibration current in Column C.            Record results (relative flux) in Column D.
l         A      l           B    l       C        l          D         l Channel    l Meas. Voltage l Meas. Current ICal. Current         Relative Flux l N41A (upper) l               Vl         . pA l          pA            ,
l                l . i t 51      l    ll$ .L      l 297.{r         l     . > f 6 f'     l l N41B (lower) l               Vl              pA l          pA l                       l l                l~ .I3G\        l l 3 (. . l     i 3OM             I      N 2. 7--     l l N42A (upper) l               Vl              pA l          pA l                       l l               l   .  'o c t    l t d .o         i  2 r6 .2       i       37o 4        l l N42B (lower) l               Vl              pA l                l                    l l                l  . ' L 'I l   l   1C9 3        l 701,(,pA      l   . 3 (,3 7       l l N43A (upper) l               Vl              pA l          pA l                       l l                l      4/A      l     iv /r4     l    rs[<9        l        v/n        l l N43B (lower) l               Vl              pA l          pA l                       l l
l N44A (upper) l l      n /f-    l      ' < /4    t    'J fA        l        nh         l Vl               A l                 l                   1 l                l .lott         I    iCl.L       l 23 N pA        I   M2ib            I l N44B (lower) l              Vl                  l         pA     l                   I l               l    1035       1 101-  ^ pA   l 7-(,13         l
                                                                                                   . ;U b           l
                         /       13.3.5    Complete attached page to calculate quadrant tilt.

l UNbI                                                  h            PT/1/A/4600/08B q                                y[                           Page 3 of 3
[. / )             Retype   #2 ENCLOSt'RE 13.3 QUADPANT 11LT CALCULATIONS Quadrant Power Tilt Calculation:
Each upper or lower relative flux (PI) is divided by the upper or lower average relative flux (RfA or RIB).
RfA =       [Rf(N-41A) + RJ(N-42A) + Rf(N-43A) + Rf(N-44A)) + N
               =     [ . 3 7 6 7 + ,370 k. +            tl/A.
                                                                + N7N)+
                                                                      . .g 3   =  1   3 RFB =       [Rf(N-41B) + Rf(N-42B) + Rf(N-43B) + Rf(N-44B)) + N
               =     [,N N 2. 2.-  + ,3(p 3 7 +          M/A    + =3I77)+         3   = '      3bl)
Where N = # of operable power range detectors                                                                     !
NOTE:       N/A tilt if detector is inoperable.
("~' ^} =        )IbI TILT (N-41A)      =
MA
                                                                  'g g Cg 3#193
(     ^
TILT (N-42A)      =                 =        370d                    ,
RfA           ,3543         .Mh TILT (N-43A)      =      Rf(N-43A) ,         3,j/              g RfA              gj /A
('    ^
TILT (N-44A)     =                 =        47 5 b       ('gg RfA            ,354b TILT (ht-41B)    =        (        =       . NNL RfB        ,
3cm           (*\\7 TILT (N-42B)     =                 =         3631               q{                                               i RFB            3 5 q -)       .
TILT (N-43B)     =         ( ''     =        N!d               C RTB             g/g RT(N-44B) ,        ,3p7)
TILT (N-44B)      =                                        ,q     3 UB             ,3gq}
Enclesure Completed By                                      Date _
Calculations Verifted By _ _,               .___.
Cate _ _           __
l l
l

Dx_ilHE98Y 9E_NUGLE88_EgMEB_EL8NI_gEEBBII9NziELUIng,_8Np.                                                                                                                                                                            PAGE 21 0                             '
IBEBU99YNBUIGS QUESTION! 5.18                                                                                             ( 1. 00) iThe. fallowing "present plant conditions" exist:
:.. Unit. computer IS. NOT . avail abl e
                                          =CRDM Number.CD2-3~Lis ' immovable" Bank D'is at'175, steps
: Power ' Level-                                                        . =                      +99.8 percent'(avg NI reading)
Tavg = 590.8 degrees F (control panel reading)
                                           ' Boron' Concentration n'*872 PPMB (last Chem sample)
PZR Pre'ssure = 2235 psig" (control panel reading)
                                           'Cyc1'e'Burnup a ~3500 MWD /MTU (Eng NSSS Log reading)'-
LUsing _the above conditions AND Attachments 5-5 through 5-12,_
ECALCULATE the "Available Shutdown Margin .(SDM)",
                  'SHOW-ANY REQUIRED CALCULATIONS - NOTE ALL ASSUMPTIONS
              . ANSWER                                                           5.18                                      (1.00)
See Master Key Attachment Assign point' values as listed'on Master Key Attachment Carry'any. errors forward-
                   ' REFERENCE-
         -           T&O CO-ROO50, Element #6; Catawba LP OP-CN-RB-HO; Pg lig
                  - LPSO Obj ective 4b;' Technical Specification LCO & Bases
                     -3.1.1.'1'AND OP/0/A/6100/06; Enclosure 4.3 & Unit Data Book KAIR 3.5/3.7
>                  1192OO2K113                                                          ...(KA'S)'
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
._....__.m_____.u_.-_.                      . _ _ _ _ _ _ _ __ _ _ _ . _ _ _ . -          _..________.__.___________.___-.-________.-___________.m___.m._____.         m._____--._m_____mm_m_._m______-____.____________._._._______._________,-

y v,y
                                -~vv                   .y 7                                                        .
0.9                                 % nit lKEM                                oPtotAts1wtos FIACTIVITY BALANCE CALCULATION Page 3 a 3 Retypa # 11
    -           .                                      SHUTD0VN MARGIN - UNIT AT POVER 3.0 CA14ULAT10N-      ~                                                                                                                                             p -T7 N                                                                ,if 3.2.1            Present Conditions                                                                                                                                                -
a;      Date
: b.      Time
: c.      T,y                    '$~ '7 0 , 9                                         'T
: d.      Present Power                                                     F/,9                % FP
: e.       Burnup                  7 T C 0-                                                  HvD/KIV (P1458) f'.
: f.       Boron Concentration                                                     f'72-          fpeB NOTE:           The sign in parenthesis indicates the sign of data to be included in calculation.
3.2.2           Required Shutdown Margin
: a.       Technical Specification Limits                                                                                   (-) 1300 pcm
: b.      -Additional Combined Immovable /Untrippable Penalty (Prom Data Book Table 6.3.4)
CRDM Number               O I) 2                                   ')          Additional Penalty (-) N2pcm
: c.      Total required shutdown margin                                                                                     (-) / N 2-pcm (Step 3.2.2.a plus Step 3.2.2.b) 3.2.3            Total Available Rod Vorth (less worst case stuck rod and uncertainty):
(From Data Book Table'6.3.3)
(-) '[2 / b'pcm                                    I 3.2.4           Rod Vorth of inserted rods (Prom Data Book. Table 6.3.1, HZP No/ Equilibrium Xenon)
Bank                                     ni                steps withdrawn                             (+) i CO pcm 3.2.5           a.      Power Defect at present power level                                                                                  (+) lE d pcm (Step 3.2.1d) and boron concentration                                                                                                                    j (Step 3.2.1f) (Prom Data Bock Table 6.0)
: b.      Vorst case flux redistribution allowance (Proz                                                                         (+) 2CN pcm Table 6.3.3 of Data Book)                                                                                                                                 !
1
                          . N0''E :        The value of Step 3.2.6 shall be more negat:ve than the total pcm in Step 3.2.2.c per CNS Technical Specification 4.1.1.1.1.
                                                                                                                                                                                      ~
3.2.6          Available Shutdewn Margin                                                                                                        (*) ]CIVPC*
(Algebraically add Steps 3.2.3 through 3.2.5)
Calculated b-,                                                                                            Cate.T. e Verified by                                                                                              Cate/T::e
(
r

INTES:A A00 WORTH (pcm) h/TY NM/nN~ h (
                                                                                                                                                                                                              ==                  6                 m n w                                                            6                w a a a                                                                           m o
             ,,, , o                                                                                                                                                    a           n                a            a u                                     +,
6    _
                                                                                  +..                  -
                                                                                                                       +
L --
                                                                                                                                                                 ..u - ;                              .                                             .                .
i
                                                                                                                                                                                                                                                                                                                                                                                                                        ,iy , *,
                                                                                                                                                                                                                                                                                                                                                                                                                            . rm 4      ..                                                                     -
rr -:::
l
                                                                                                                                                                                                          ._4              .                                                      -:
g c:r=              c-- - :t                    it+                     1:       - - - -
7tr-r/- 45,                                            .._
_1-.:.           _L::_
                                                                                                                                                                                                                                                                                                                         ..-...                                   '!_              t'
                                                                                                                                                                                                                                                                                                                                                                                         .e 4    i6..       u. ,j .:;             . -.;;__
F.J. .-.
                                                                                                                                                                                                                                                                                                                         ..      _.      y--                                                      .         , .                 ...
                                                                                                                                                                                                                                         .          _                                                      ::c-         _.-.
                                                                                                                                                                                                                                                                                                                                                                 ./.    . .%                            .u.                            .
            , m. ,,                                                                                                                                                                                                                                                                                         =---r-                                   f isaz.: .14 t r+
m
    ' 1,                                                                                                         ,     (
                                                                                                                                                                                                                                                                                                                     -4TJ. n. -
                                                                                                                                                                                                                                                                                                                                                                          -;rr+ - . ..4-e.                 . . .
__- u                        ..-_                                         4 .u c.s. ~.
M                                                                                                                                                                                                                   54            .
                                                                                                                                                                                                                                                                                                                                                            ++_        .
g=
                                                                                                                                                                                                                                                                                                                )_. ,                               .                             --                                  -
22
                                                                                                                                                                                                                "+"                    =                  _::._:::t                                  /'_:. _:-=:                                                 .;--.    ._qi                ::.                t-- .**.~     :.r--
                                                                                                                                                                                                                                                                                       )               .                                                                           -.      :t.r*- +~*.
:. )g
                                                                                                                                                                                                                                                                                                                                                   ..            _..       +                      ,        g.
                                                                                                                                                                                                                       .+
                                                                                                                                                                                                                                                                                                                                                                                        . .           ..n.                .
                                                                                                                                                                                                                                                                                                                                        ~~~~
        ,   , ,Fu ,,a u
g.98.,                                                                                                                *i
                                                                                                                                                                                                                                      ~.~4'+.[-.
                                                                                                                                                                                                                                                                                  -- -:-.:F
                                                                                                                                                                                                                                                                                                                                                                               ** +''                      *-
__._               _~'             y
                                                                                                                                                                                                                ,-.y                      ar                                                        -           -.           -.
7--n-_-                               -. . . - ,
m                                                                                                         3/*                 .        --.__
3:                                                      ._         -    .
a4 .                +
oh. IE& , o ___                                               .,._,                        o as c45                                                                                                     ~
                                                                                                                                                                                                                                                 =        ---                   -
                                                                                                                                                                                                                                                                                                                                                                                        .i.u            _ 44              . . . _          C 7               --      --     -
n       ..
                                                  .              --             .                    8 i s.e                .g                                                                                 :Ar
                                                                                                             >* M                                                                                             #                                                                                                                                                                                  #      ,_                  .              cm tg   2.4 e os o                                                                                                                                                                                                                                                                                                                                   r*
sN2                                                                                               .L'~_;ur       4_
                                                                                                                                                                                                                                                                                                                                                                                        .1              .-
                                                                                                                                                                                                                                                                                                                                                                                                                            ~-
m i,) m I
O g
w                                                                      g                        p g                                                              _
f p                                 ,   ,
u-;;;- .-:.-
r&
s- --         - -      ----                  ---
: w. . _-.                       _-..
yg
                                                                                                                                                                                                                                                                                                                                                                                                                                           ,e o                                                                                              g                                                                                                         m. n 4
                                                                                                                                                                                                                                                                                          .-         ::q-r=             .___.                 -
                                                                                                                                                                                                                                                                                                                                                                          +~
r--
g   x, y,            c-
                                        , g '__                                                                                                                                                                                                                                                                                                                                                                             __
                                                                                                                                                                                                                                                                                                                                                                                                                                           .,                    2
                                                                                                                                                                           /                                    ..J 1:1 ==rrs=4                                                                                          z;t                       "      ----
                                                                                                                                                    ~
                                                                                                                                                                       -,e
                                                                                                                                                                                                                     ~:: s_.x                           -                                                          -                    "-
                                                                                                                                                                                                                                                                                                                                                          +-v.-.                                                                               :P:
G *C C
                                                                                                                                                                                                                                                                                                                                                                                                                                                              ,Z.
n
                                                                                                                                                       ++d                                                     --
[ m        ::t:---.r_            L*r-L -:                                .=t nT :                              -ag .
                                                                                                                                                                                                                                                                                                                                                                                                                                                   @             Q
                                                                                                                                                                                                                          .                                                                                       r2_ :
z, n       ,
g
                                                  +     _
                                                                                                                        -u_                   44_ -I-                                                                  tr ;;4                            .__._x-- r2 t.: :                                                                                ~~                                                                               M       :
                                                                                                                                                      &                                                                                                                                                                               J '*                                    c                                             : t.:                         rn r:=n: 'b's 2'E ,r:r.~L                                                                           ~.J::                                                                 *
                                                            .                                                                                  su                                                                                                                                                                                                                                                                                                  .n
                                                                                =e4           ..                                                                                                                                        .
u           4+-                                                                                                                                           r                  *r~ ::                             "       -
o cy4_,                         = - - -
                                                                                                                                                                                                         -g                               ;-.          ;_-n...                                           ;      ,;      :::             -g21; g-
                                                                                                                                                                                                                                                                                                                                      ,;-                                               ...;                  :             ;; .           o$
                                                                                                                                                                                                                                    =.:                                                                                                                                                                                                                   Ch 3
:f.              -                                                             -
:=: = :t                               -
:=3:-                                            1:::-                         -*-
tr in                                       k:      w>
_ .4 e.-              4
__.fr.                     +.                                                                 g;.                     ::. r- r t              -   . _;:                                    t r            :!
                                                                                                                                                                                                                                                                                                                                 -       ~
tT L:t ::: r:.. . . ;;.
E: .re:t ::: irr: ~. : -_
j
                                                                                                                                                                                                                                                                                                                                                                                                                                           .- d[ E
_.-        4    . --
                                                                                                                                                                                                              ..                                                           -t                                            r:                                                                                                                                ._. c=
S     . _o.
                                                                                             =4                 :-_ r:t- n,.                                                                                                                              .._
3                              .       .              ...                ...             ...            ...                               .._            o       --
8,
: 2.,2                                                        { ff
_.{                           r       ;tgrg,                                                         ;-f g. .tr_a ._:.4 :. ;i. .a._s.: :::                                                              _. : :_        c.      m.             3 c y
_a            5+.           +++                                                 __-p 7~                                                                  ..                                    ...e
                                         .                                                   ...             ,r             .
4.,4 .
g .:.
o                    ,,
4                            r          -e__.                            _-..                                                                             -               ...
                                                                                                                                                                                                                                                                                                     ,T
                                                               .m':i; ._;:
:r_;;;                                         =.                                              -+. :;                                  -
ig                                                                         -
jj t ,.y .4 ::.                   :4 gpt                          L                                         ,s                                                          j..            ::                                                =
                                                                                                                                                                                                                                       , _ .                               .. E' l
                                                                                                                                                                                                                                                                          ..-                                   .        .                -.                              ...             ...          ,:3.
_w, L
                                                     *4---.
_+
:.u
                                                                                .-s
[L
:t hTI rt ;
                                                                                                                                                                                                                                    ++t- -}.:t -'r1 t: "t:
                                                                                                                                                                                                                                                                                                              -:         M: 4:. ::
7:t 't.n rt:
r;:
i r*- :*r r:.            7:
3
                                                       .t            a             e             5       6                                .,                               .4        -                                                 rfT i..t                                                                              *
* _ a'I -.a._r.m_,.2_-*r1.t..r r**
                                        .g -. u. .._ prr. .r +        _,
                                                                                                                    .                                   r, ,
                                                                                                                                                               -.           _4 4_
                                                                                                                                                                                                               -r tH                                  .-
H4 4,. +f p. -;.rt. u. . .r; tri                                                                                 .;- r..g                      ,..
                                                                                                                                                                                                                                                                                                                                                                  .r w
                                                                 .            z.                 e       >          +-                                  .,..            ...,..
w
                                                                                                                                                                                                                                            .r.
_                       _.. . , r                      -,             -
_ ...  ..                                         ..~.
                                                                                                                                                                                                                                                                          -r+4
: r. . .n. ;x. ;.
                                                                                                                                                                                                                                                                                                                        ~.                    ..
a..   ..
u.
                                                                    --f
:t-b                             ._
2               .,                             _.                 4           .
_ . . . -                            :t                        ru                 nt ter                                               -                              --
4:r r.--: : :t-r-
                                                                                                 -   _.                                                                     _ _ . .                                                          :t m                                                                                                         t:-                                 -               -
a                          wi.                                  .                     .                           ---,                             - - . _ -                               ..                             ;;.,m p.
                                              ..~4'.ft4 nti =                                                         ~+             -         -4 ~-,                                               -4:.                                                 :11.41.;                                    g. , 14             .;            1n                  ...
                                                                                                                                                                                                                                                                                                                                                                          ;:u            .               .
ry:y                                                                                                                                                                                       ta:                                                                                      ; tu                      111             .:                                                            -
_         ____              ,      _$    . __,.                       _              -,      ,     _ , .      7,_._,.                                             ,,
                                                                                                                                                                                                                                                        . _;               gn                        ..
3           ,
                                            ):t,,.                _-_               _       4._--                     _--
                                                                                                                                                                                    . __ . . a--!                                     <     n,.;          Hr rt: H:                                                           7 r r r;- :,,                       ,. , :          - -
m
:                                                                                    u
                                                                                                                                                                                    . _ . . .gr gg                                                                           :p n.                                                                                                             A,
                                                                                                                                      +,
2                                                                                      .                                         ,.
27                                                                                                                                                                                                         7.a -,; j,,g p.                                                , :- y n, .., ,, ,,
n y                                                                                                                                                      ,
c                                                                                                      r*
l:r nt.va
:2                ta:m.                          :-2 r :               4r,.:t
                                                                                                                                     .*+12- :::::t ... . .s~..--ln:                                                 -- rit            c:                  -v               P:
f::-ri tit !'hi : - t r- :rt :- "
:: ru ::-                                                               -
i
                                                                                                                                                                                                                                                                                                                                                                                                                                      .1 4:;
i
                                                                                 ._. m..
o E1 JI ....                                            ....
                                                                                                                                                                      ---           _... .......           ..                               , ...                         a..                                           . ..                 ..
I!l N aid -* 'lEl III                                                                                                                11112 ;J.1717:*                                             :*I                    18                                     *2Ii                a       I      I1                 IfI c, c. ,
tu " M '                                                                                                                                                                                      '                                                                                             '_
Km!  .r*
M                                                                                                                                                                                                                                                                                                                                                                                                                                                          ,
                                                                                                                                                                                                                                                                                                                                                                                                                                                       ' G =T x tr,
                                                                                                                                                                                                                                                                                                                                                                                                                                                                ;'as e.as i          d D'-9                                                                                                                                                                                                                                                                                                                                                                                                                                                   ,
4                                                                                                                                                                                                                                                                                                                                                                                                                                                 .9 m                                                                                                                                                                                                                                                                                                                                                                                                                                               N M
m                                                                                                                                                                                                                                                                                                                                                                                                                                                 ~'
E                                                                                                                                                                                                                                                                                                                                                                                                                                                  ~
j !w   .
QQiem $b                                                                                                                                                                              .

             ///72[& /                    h        ENCLOSURE 4.3                        Page 1 of 3 OP/0/A/6100/06                       Retype # 11 REACTIVITY BALANCE CALCULATION
    ',  .                                   SHLTDOWN MARGIN - UNIT AT POVER                              i 1.0 INITIAL CONDITIONS 1.1  A. determination of the shutdown margin with the unit at power is
                         ' required.
2.0       PROCEDURE 2.1  If the' reactor is criticak (Modes 1 or 2) and aB full length control rods are movable and trippable minimum shutdown margin exists provided the control rod insertion limits are not violated, per Technical Specification 3.1.3.6.
2.2  If the reactor is operating with a known immovable or untrippable rod, the shutdown margin shall be calculated by completing Ee-tion ''.
as follows:
3.2.1      Record present NC conditions:
(a, b)     Date and time.                                          j j
(c)        T,    from computer points A0860, A0861, A0362, A0863 or the control panel.
(d)         Present power level f rom P1385 or NI power.
(e)         Cycle burnup from computer point P1458 or Reactor Group Duty Engineer (NSSS Log) .
(f)         NC Boron concentration from the latest available       ,
Chemistry sample (OAC Program General 68).             I 3.2.2      (b)         Record the immovable /untrippable rod number and any additional penalty for combined immovable /untrippable rod worths (found in Data Book Table 6.3.4).
(c)         Determine and record the required shutdown margin.
Add any additional penalty for combined                   j immovable /untrippable rods to the required Technical Specifications shutdown margin.
3.2.3      Obtain and record the total available rod worth during any point in the core cycle from Data Book Table 6.3.3.                       j l
3.2.4      Determine the 537'P rod worth at H:'P, No/ Equilibrium Xenon of       l all control rods that are :,nserted in the core at the present      j time from Table 6.3.1.
1 3.2.5      Obtain and record the pcwer defect at the present power level       1 (Step 3.2.1d) and boron concentration (Step 3.2.lf) from Data Book Table 6.e and the worst case flux redistribution a.lcLance f rom Dat a sock Tab' e 6. 3. 3.
1 Quedica $ .( b u_______-___--_--__-

p.
        'l7[/9(Hmfm7 T- T                     ENCI4SURE~4.3                   PagsL2 of 3 OP/0/A/6100/06                   Ratyps # ~11
          .                           REACTIVITY BALANCE CALCULATION SHUTD0VN MARGIN - UNIT.AT POWER 3.2.6     Determine the available shutdown margin. Sum the values obtained in Steps 3.2.3, 3.2.4 and 3.2.5. This value
                       .       shall be more negative than -1300 pcm shutdown margin plus any additional penalty for an inoperable rod found in -
Step 3.2.2 per CNS Technical, Specification 4.1.1.1.1.
If.this.value is not more negative than that'in Step 3'.2.2.c, borate per .0P/1(2)/A/6150/09 (Boron Concentration Control)
I                              until this shutdown margin is reached.
2.3 Transmit a copy of completed Enclosure to the Reactor Engineer.
I

                                                                                                                                           - p V
L
           ;/   $               $ $1(AA7"' ' f5[ ENCLOSURE 4.3                                                     Unit
: h. !
* OP/0/A/6100/06                      Page 3 of 3 L. .
REACTIVITY 3ALANCE CALCULATION                      Rotypa # 11
  ..           .                                              . SHUTDOWN MARGIN - UNIT AT POWER
               ~3.0          CALCULATION.
                           -3.2.1-              'Present Conditions
                                    .,            a:    Date
: b. Time c.
T,y,
                                                                                                 'F
: d. Present Power                                     % FP
: e. Burnup                                         MVD/E'U (P1458)
: f. Boron Concentration                                  ppmB N0'E :               The sign in parenthesis . indicates the sign of data to be included in
                                                 . calculation.
3.2.2                Required Shutdown Margin
: a. Technical Specification Limits-                                    (-) 1300 pcm
: b. Additional Combined Immovable /Untrippable Penalty (From Data Book Table 6.3.4)
CRDM Number                                 Additional Penalty (-)            pcm
: c. Total required shutdown margin                                     (-)        pcm (Step 3.2.2.a plus Step 3.2.2.b) 3.2.3                Total Available Rod Vorth (less worst case stuck rod and uncer.ainty):
(From Data Book Table 6.3.3)
(-)          pcm 3.2.4                 Rod Worth of inserted rods (From Data Book Table 6.3.1, HZP No/ Equilibrium Xenon)
Bank                steps withdrawn               (+)       pcm 3.2.5                a. Power Defect at present power level                                (+)       pcm (Step 3.2.1d) and boron concentration (Step 3.2.lf) (From Data Book Table 6.4)                                              ,
: b. Worst case flux redistribution allowance (From                     (+)        pcm Table 6.3.3 of Data Book)
NOTE:                The value of Step 3.2.6 shall be more negative than the total pcm in Step 3.2.2.c per CNS Technical Specification 4.1.1.1.1.
3.2.6                Available Shutdown Margin                                                 (~)       PC*
(Algebraically add Steps 3.2.3 through 3.2.5)
Calculated by                                                              Date/ Time Verified by                                                                Date/ Time l
                                                                                                           .                                    I haf$h06 ha                                                        i
                                                                                                                                                \

p yyy   vvvv- - -        ~     ~
v                                       ~ ~s                                        {
'.1                                                                         PREPARED BY H.W. Hawes l
OP/1/A/6700/01 UNIT ONE DATA BOOK-I TAB'LE 6.3.3 Catawba 1 Cycle 3 TOTAL AVA IABLE ROD VORTI H2P, NO XENON
: 1. THE MININUM TOTAL ROD VORTH AVAIIABLE           6902 pea DURING CYCLE
: 2. MAXIMUM STUCK R00 WORTH DURING CTCIZ            1108 pen
: 3. TOTAL ROD WORTH VITH HIGHEST ROD STUCI          5794 pea
: 4. IISS 10% UNCERTAINTY (3 x 0.9)                  5215 pca TOTAL AVAIIABLE ROD VORTH IS                    5215 pea
                                           ?                                                                                      1 VORST CASE FLUE REDISTRIBUTION ALI4WANCE                                                              d (for S/D Margia Calculations w/ Unit at Power):       204 pca                                         l i
l Gedise GA

PREPARED BY M.W. Hawes m                                                                                              OP/1/A/6700/01 UNIT ONE DATA B00K                                                      l TABLE 6.3.4 l
INOPERABIICONTROL R0D WORTES l
K2P
                                                                                                      ~
CRDM          CRDM         WORTE         CRDM          CRDM         VORTH NUMBER               LOCATION       (pca)        NUMBER       LOCATION       (pca)
          .                                                         SA2 1          8-4           51         CA1-2          E-10          740 CB2-1          86           745         5El 3          R-12          432 CCl-2          38           268         CC1 3          E-14          268 CB1 2          8 10         745         $82 4          J-3           490 sal-2          8 12          51         581 3          J-13          490 SD1-1          C-5          778         C82 4          E2            745 582-1          C7           490         CC2 4          K-6           740 581-2          C9           490         CA2 2          E-8           740 5C1-2          C-11         774         CC2-3          K 10          740 SA1-1          D-2           51         C81 3          E-14          745 CD1-1          D4           778         3D1 4          L-3           778 SEl-2          D8           432         SC1 3          L-13          778 CD2 1          D-12         778         SA2-4          M-2             51 SA2 2          D-14.         51         CD2 2          M-4           774 SC1-1          E3'          778         SEl-4          M8            432 SD1-2          E-13         778         CD1 2          M 12          778 CB1-1          F-2          745         1Al-3          M 14            51 CC2-1          F-6          740         Sci-4          N5            778 CA2-1          F-8          740         581-4          N-7           490 CC2-2          F 10         740         582 3          N9            490 C82 2          F 14         745         5D1 3          N-11          778 581-1          G3           490         sal-4          P4              51 582-2          0-13         490         CB1-4          P-6            745 CCl-1          E-2          268         CC1-4          P8             268                       j SE1-1          H4           432         C12 3          P-10           745 cal-1          H-6          740         SA2 3          P-12            51 CD2 3          H.8          482 Note: If more than 1 inoperable control rod is known to exist then use the worth from the table above for the bishest worth inoperable rod and add 1108 pca for each additional k.nown inoperable rod.
1 gdiew E*N

    ,,.,         n ,,            -.                 ,,                                                         -
PREPARED BY M.W. Hawes s
OP/1/A/6700/01                     Page 1 of 2 UNII ONE DATA BOOK TABLE 6.4 TOTAL POWER DEFECT (pce) AS A FUNCTION OF pct'ER AND BORON CONCENTRATION AT 80C (0        50%)
BORON l CONCEN- l                              POWER LEVEL (%)
TRATION l (PPN)      l   0   5      10     15     20    25     30      35     40      45    50 l
I 600 1      0 113     227   340     454   564    665     762    860     957 1055 625    l   0 112     225   338     451   565    661    758     854     951 1048 650 l      0 112     224   336     448   561    657    753     849     945 1041 675 l      0 111     223   334     446   558    652    747     442     937 1033 700 l      0 110     221   332     443   554    648     742    837     931 1026 725 l      0 110     220   330     440   551    644     737    831     924 1018 750    l   0 109     218   328     437   547    639     752    8 25    918 1011 775 l      0 108     217   326     435   544    635     727    8 19    911 1003 800 l      0 108     216   324     432   540    631     722    8 13    904   996 825    l   0 107     214   322     429   537    627     717    808     898   989 850 l      0 104     213   3 19    426   533    622     712    801     891   981 875    l   0 105 f 211     317     423   530    618     707    796     885   974 900 l      0 105     210   3 15    420   526    613     701    790     478   966 9 25   1   0 104     209   313     410   523    610     697    784     871   959 950 l      0 103     207   311     4 15  519    605     692    778     865   952 975    l  .0 103     206   309     412   5 16   601     687    772     858   944    5 1000 l        0 102     204   307     409   5 12   596     641    766     851   937 1025 1        0 101     203   305     407   509    592     676    760     844   929 1050 l        0 100     201   302     403   505    588     671    755     838   922 1075       l  0 100     200   301     401   502    584     666    749     831   914 1100 j        0  99     19 9  298     398   498    579     661    743     825   907 1125       l  0  98
* L9 7    296     395   495    575     656    737     819   900 1150 l        0  98     196   29 4    392   491    571     651    731     811    892 1175 l        0  97     19 5  292     390   488    567     646     726     805   885 1200 l        0  96     19 3  290     387   484    562     641     7 13    798   877 Qang,, DB

ycy-      - -.         - ~~
o-      y    .
CORGwM 1 Myde' 3~
P'                                                                                                                              PREPARED BY M.W. Hawes l
OP/1/A/6700/01                                                              Page 2 of 2 UNIT,ONE DATA BOOK TABLE 6.4 TOT?l POWER DE E'  C T (pca) AS & FUNCTION OF POWER AND SORON CONCENTRATION AT SOC (50 - 100%)
1 BORON l CONCEN- l                               POWER LEVEL (%)
TRATION l (PFM) l        50    $$      60    65     .70     75                            to                         85   90    95    100 I
I 600 l 1055 1152 1249 1346 1443 1541 1639 1734 1837 1936 2035 625       l 1048 1144 1240 1336 1432 1529 1626 1724 1822 1320 2018 650 l 1041 1136 1231 1326 1421 15 17 1613 1710 1807 1904 2001 675 l 1033 1127 1221 1316 1410 1505 1600 1696 1792 1884 1984 700 l 1026 1113 1212 1306 1399 1493 1587 1682 1777 1872 1967 725 l 1014 1110 1203 1295 1388 1481 1574 1668 1762 1856 1950 750 l 1011 1102 1194 1285 1377 1469 1561 1654 1747 1840 1933 775 l 1003 1093 1184 1275 1366 1457 1548 1640 1732 1824 1916 800 l 396 1085 1175 1265 1355 1445 1535 1626 1716 1807 1898 825 l         989 1077 1166 1255 1344 1433 1572 1612 1701 17s1 1881 450 l 981 1068 1156 1244 1332 1421 1509 1594 1646 1775 1864                                                                     l 875- l 974 1080 1147 1234 1321 1609 1496 1584 1671 1759 1847                                                                    j s00- l s46 1052 n38 1224 in0 1397 1483 1570 1656 1743 1830 925 l         959 1044 1129 1215 -1300 1346 1471 1557 1642 1728 1814
              .         950 l s52 1036 n20 1205 12e9 1374 1458 1543 1627 inz 1797 975 l 944 1027 till 1195 1279 1363 1646 1530 1613 1697 1781 1000 l 9 37 lois 1102 1185 1268 1351 1433 1516 1598 1681 1764 1025 l         92s 10 n 1093 n75 1257 1339 1420 1502 1584 1666 1748 1050 l 922 1003 1084 1165 1246 1328 1404 1689 1569 1650 1731 1050 l 922 1003 1084 n65 1246 1328 1404 1489 1569 1650 1731 1,075      l   914   994 1074 1155 1235 1316 1395 1475 1555 1635 1715 1100 l 907 986 1066 1145 1215 1305 1383 1462 1540 1619 1698 1125       l   900   978 1057 1135 1214 1293 1370 1648 1526 1604 1682 1150 l 892 969 1047 1125 1203 1282 1358 1435 15 n 1588 1665 1175 l         885   962 1039 ins 1193 1270 1345 1421 1497 1573 1649 1200 l         877   953 1023 1105 1181 1258 1332 1407 1482 1557 1632 l
1 l
pnU*' $,l6
{

PAGE 22 1Dt_2IBE98Y_9E_NWRLE88_E9 WEB _EL8NI_9EEB8II9Nx_ELUIDSz_8ND^
L                   IUEBM9DYN8 MIGS e
Y.!.
                   '.l l-10UESTION: 5.19                   ( 1. 50)
NOTEtz For the following questions - DISREGARD'ANY ENERGY INPUT FROM REACTOR COOLANT SYSTEM (NC) PUMPS, CHARGING FLOW,tAND NCP SEAL IN-LEAKAGE AND ANY ENERGY LOSSES
                       .FROM LETDOWN AND PRIMARY SYSTEM PIPING.
:Given that'the. rated thermal' power of each Catawba Unit core.
Jim 3411,Mw(t) and that the specific heat is approximately
            ~1.39 BTU /lbm - Degree F:
NOTE: For "a" ~ & 2"b" below, SHOW AL'L CALCULATIONS AND NOTE ALL ASSUMPTIONS
            'a)        During normal loperations, what flow rate (in Ibm /hr) is-required to keep.tho, temperature across the reactor'l vessel at. SIXTY (60) Degrees F7 b)       During . normal' operations, what is the approx. enthalpy rise / change (in Delta' h) across the reactor core?
            .c)        With' a reduction in NC flow and rated thermal power remaining'at 3411: Mw(t) the enthalpy rise / change across the' reactor will INCREASE / DECREASE / REMAIN THE SAME.
ANSWER          '5.19            (1.50) a)       3.413 (E +6) BTU /hr X-3411 Mwit)           = 1.1642 (E +10) BTU /hr 1.1642-(E +10) BTU /hr = (fl ow rate) (1.39 BTU /lbm-F) (60 dT) 1.1642 .(E +10) / (1. 39) (60)       = 1.3959 (E +8) lbm/hr CAnswer allowance - between 1,38 (E +8) to 1.41 (E +8)]
(0.4 - calculation; O.1 - answer) (Errors Carried Forward) b)       1.1642 (E +10) BTU /hr = 1.3959 (E +8) lbm/hr (Delta h) 1.1642 (E +10) DTU/hr/1.3959 (E +0) lbm/hr            =  83.4 DTU/lbm LAnswer= allowance - between 82.6 BTU /lbm to 84.4 BTU /lbm]
(0.4"- calculation; O.1 - answer) (Errors Carried Forward)
            . c) '     INCREASE (0.5)
REFERENCE
            ' Catawba LP OP-CN-HO-HT; Pgs 3 & 4; Catawba LP OP-CN-CTH-CTH; Thermal and Hydraulic Tables; Pgn 16 & 17 KAIR 3.1/3.4-
             -193OO7K108             ...(KA'S)
L                                 (*****     CATEGORY 05 CONTINUED ON NEXT PAGE *****)               i u
E                            -          -     - - - - - _                                            l

4          $
         ,5; i ~ THEORY QF'NUCLEAN POWER PLANT OPERATION,_ FLUIDS1 _AbD.                                                                      PAGEL 23' THERMODYNAMICS
   .e.
QUESTION                       5.20                    (7.00)
         ' Using'the data below AND steam tables, CALCULATE the associated' percent-THERMAL. power output of the NC system.
                               ^
           'NOTEt-Assume all reactor thermal output is placed into the secondary --Disregard any energy input from_the reactor' coolant' system (NC) pumps,' charging flow, and-NCP seal in-leakage and any energy (heat) losses ( om letdown,' blowdown and primary / secondary system piping.
_ _ _ _ = -                  _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -    ___________________
            .I .                    Present; Power Range Instrumentation Readings: 100 percent
                    .F Control Bank Positions: .Gp C m 230 steps- Gp D = 220 steps
           . I I '.                 Present MW('e) .( gross): 1098 = 97.6 percent IIII. Feedwater. Temperature: 431'.9 Degrees F Feedwa'ter Flow                                    Steam Pressure
                                 . Loop               C(E +6) lbm/hr]                                          (PSIG)-
A                        3.672                                              1002 D                        3.674                                              1001 C                        3.669                                                998 D                        3.672                                              1003
            - SHOW ANY REQUIRED CALCULATIONS - NOTE ALL ASSUMPTIONS l.
l L                    _ _ _ _ _

7   . -
m      ,.
          ; 5i__IUEQBy_QE_NyCLE88_EgNEB_EL8NI_QEEB811gNt_ELQ10@t_8ND                                                        PAGE                   24 IMEBMODYUBMIGE
      .            c.
                        )
ANSWER'                5.20       (2.00)
Steamisystem enthalpy for each loop'=
* 1193 BTU /lbia                              (0.1) y           _ Feedwater enthalpy for each loop                 =  (-)
* 410 BTU /lbm-                              (0.1) e Enthalpy Rise / Change =           783 BTU /lbm                               (0.2)
Loop AL* Power Out e 3.672 (E +6) X.783 =                   2.875 (F +9)                                (0.2)
Loop 1B
* Power Out = 3.674'(E +6) X 783 =                  2.877 (E +9)                               :(O.2)
Loop'C'* Power Out = 3.669 (E +6) X.783.=                   2.873 (E +9)                                (0.2)
Loop.A
* Power Out = 3.672-(E +6) X 783 =                   2.875 (E +9)'                               (0.2)
                                                                                   ~
Total Power Output     =
* 5575~~~lE +9)                                 (0.2) 11 5          (E +9) BTU /hr.
             .______________________             = ~.3369.5 MW/3411 MW =
* 98.78 % RTP.
3.413 (E +6)' BTU /hr/hW
              '(0.5 pts for " BTU /hr-to-MW" conversion - 0.1 pts for answer)
[ Answer allowance - between 98 % RTP to 99 % R'iPJ EGive Full Credit' If " Average" FW Loop Calc Performod]
[Any Errors Carried Forward].
REFERENCE T&Q CD-ROO99, Element'#2A; Catawba LP OP-CN-CTH-CTH; Thermal and Hydraulic Tables; Pgs 16 & 17; Catawba LP OP-CN-HO-SLC; Pgs 14-16; PT/0/A/4220/01; Enclosures 13.10 & 13.11
            ' KAIR 3.1/3.3 3.1/3.4 193OO7K106               193OO7K108       ...(KA'S)
QUESTION               5.21       (1.00)
DEFINE Shutdown. Margin (SDM) as noted in the station's
              . Technical Speci fications.

E c0 L Qu ' THEORY'OF NUCLEAR POWER PLANT DEEB8IlgN s_ELUID@g_8MD                                                                                                                                                                                                                        PAGE 25 THERMODYNAMICS L*
* c     .
   ~
t; 1:
l j,         ANSWER'                                               5.21                      (1.00)
            '" the< INSTANTANEOUS amount of - reactivity                                                                                                                                                                                                  (0.1) byjwhich'the reactor IS subtritical                                                                                                                                                                                                         (0.1) or'WOULD BE suberitical-                                                                                                                                                                                                                    (0.1) from its PRESENT1 condition                                                                                                                                                                                                                (0.1) assumingLALL' full-length rod cluster assemblies / RODS                                                                                                                                                                                    (0.1)
Dare FULLY ~ INSERTED                                                                                                                                                                                                                        (0.1)
EXCEPT for (wi th the exception of)                                                                                                                                                                                                         (0.1)
L             the SINGLE rod cluster assembly / ROD                                                                                                                                                                                                       (0.1) of HIGHEST reactivity WORTH                                                                                    .
(0.1) whichoistASSUMED to be FULLY WITHDRAWN."                                                                                                                                                                                                   (0.1)
NOTE: The words " ROD" or " RODS" are acceptable substitutes for the terms " ROD CLUSYER' ASSEMBLIES" or " ASSEMBLY".
REFERENCE
           ' Catawba LP OP-CN-RB-HO; Pg 6 of 13; LPSO Objective 3; Unit
            ' Tech'ical n                                                          Specification (SDM) Definition 1.29; T&Q CO-ROO50
           .KAIR13.2/3.6-192OO2K110                                                              ...(KA'S).
i
(***** END OF CATEGORY 05 *****)

by
} ..      s 26 L ;;hz__kL8NI_gyglgMg_pE31gNz_GQNIBg(1_8ND_lyglBUMEN1811gN                                                        'PAGE
[,' QUESTION k ,01 -                      ,
(1.00)-
b Select the correct" statement concerning the Inverter Manual LBypass. Switch in.the 125 VDC / 120 VAC system.
a):The: Manual' Bypass' Switch is interlocked with the alternate source VRD breaker which must be closed in
                       . order to switch to Alternate Source to Load.
                .b) The. Manual Bypass. Switch has no interlocks to prevent manual transfer if the electrical sources are not in synchronous with each other.
c) The Manual Bypass' Switch is-interlocked with the sync
                       ' light-in such a way that you can-not transfer to the alternate. source unless the. sync light is lit.
d)tThe. Manual' Bypass Switch.is interlocked withithe sync light.in such a way.that you can not transfer to the alternate source unless.the sync light is out.
ANSWER            6.01          (1. 00) b)       (1.0)
REFERENCE OP-CN-HO-EPL
            'OP-CN-HO-EPL LPSO obj. 2.E k/a-2.G'/ 3.1 OO62000K40:           ...(KA'S)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
i

     \
t
                                                                                                                     ,PAGE 27 i;'st__E66NIigygIgdg_DggigN _gONIBOL2_8ND_INSISydgNIGIlgN                         t 1
g-               e
                                                                                    ~
          ; QUESTION. 6.02                                                    .(1.O0)
:The CA1" Auxiliary Feedwater System" Auto started on an SI
               .signald Trains A and B CA were reset to manual control using
'.           Lthe switches. labeled "CA Sys V1v CTRL"'. The valves were
             ~ repositioned to control level. The SI signal is still in.
The level in "A" S/G decreases to the low - low setpoint on                              .
Lall.four level transmitters.
CHOOSE the roost correct answer describing the CA. systems response.
a) The turbine CA PumpEstarts
                ~b) Nothing happens.
c) CA Pumps A and B and valves return to the Auto initiated position.
d)ECA Pumps A and B and Turbine. Pump and valves go to the
                          - auto initiated position.
ANSWER                             6.02                            (1.00) u-
: c.           (1 0)
REFERENCE.
System Description of the Auxiliary Feedwater System CNSD-0147-01 Sec 6.1.18 Page 23 1k/a 4.0 / 4.2 LPSO 4
            '061000K406                                               . . . (KA' S)
(***** CATEGORY 06 CONTINUED CN NEXT PAGE *****)
i m______..____.____.___.__                         . _ _ _ _ . _ _ .

r bl__ELGUI_SYSIENS_QEglgNx_QQNIBg6x_GNg_INSIBydEUISIIgN-                                                                                                     PAGE 28 L .               .
:OUSSTION                      6.03              !1.00)
During a Reactor start up and with power at 5 E-(-11) amps,
      , :a now operator takes the Operation' Selector switch from the
           ' Normal position to the l ' E- (-3 ) position on the Intermediate
           ; Range:N 35 drawer.
L           From the'following, CHOOSE the'one which best describes the system response.-
                                                                                                                                                                                  )
a) The Reactor will' trip on Intermediate Range High Flux                                                                                                           l
: Trip, and I.R. N-35 meter will read i E-(-3) amps.                                                                                                         J b) The I.R. range Hi Flux trip bistable will Trip, but no                                                                                                           ;
Reactor Trip wil1~ occure. The I.R. N~35 meter will read 1 E- (-3) amps.
c) Excepting.annunication, nothing will happen, d) Will receive a high level rod stop alarm.
ANSWER                     6.03.             (1.00)
I J
c)-
(1.0).                                                                                                                                                       !
REFERENCE Electrica1' Controls System Description END Page 3-9 OP-CN-HO-END                                                                                                                                                          j LP50 obj. 6 i
           =k/a 3.1./ 3.2 015000K604                       ...(KA'S) 1 I
l 1
1
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

st__PL8NI_gygIENg_DEgigN2_ggNISQL1_8ND_INSIBUNENIGIlgN.                                                                             PAGE- 29 L
l QUESTION                 6.04               (1.50) l
       ' Answer the f ollowing                       questions TRUE OR FALSE a) Auxiliary Foodwater Condensate Storage Tank supply CA6 automatically closes following a low - low level in the CA Storage Tank.
b). Nuclear Service Water (RN) valves to CA will not E                       automatically.open-following a loss of condensate source unless CA has auto started.
c) RC circulating water will not auto'open to the CA system on a sustained low suction pressure on the CA system.
                                                                                                                                   ,s/"     }
0/c. i o                                               w I '05 I    ci ANSWER                   6.04               (1.50) a) TRUE b) TRUE-c) FALSE                        (3 0 0.5 EA.)
REFERENCE OP-CN-HD-CA Sec 3 LPSD obj. 2 k/a 3.9 / 4.2 061000K401                           ...(KA'S) i l
OUESTION                 6.05               ( .50)                                                                                              i What TWO (2) physical conditions must be satisfied in order for the invertep synchronizing circuit to function properly?
( [          (, .o

R
   'hiU_dLBNI_EYSIEdg_DEgl@N z_CQNIBQLt_8ND_lG@IBUMEUI8IlgN                  PAGE 30     4 f
ANSWER       -6.05-Ck
(   h/
a)'The synchronizing disconnect switch          must be closed.
(0 15)
     'b) The alternate AC source breaker must be closed. ( 0,.r5       y)              (
REFERENCE                                  1
     -OP-CN-HO-EPL Page 11 'of 17 OP-CN-HO-EPL'LPSD obj. 2.E k/a 2.8 /'3.1          3.5 / 4.0
      .T&Q CO S0042 element-4 & 9 062OOOK103           062OOOK403      ...(KA'S)
QUESTION      6.06            ( .50)'
What'TWO (2) conditions will cause an inverter in the 125 VDC / 120 VAC system to revert to " free running frequency"?
ANSWER        6.06           ( .50) d a) Failure of the alternate source. (0.J6) $
eb) Alternate source goes off frequency (O.g) by more than           .7 Hz. (0.25)        (+ or - .3 Hz)
REFERENCE OP-CN-HO-EPL Page 11 of 17
     .k/a 3.2 / 3.7           2.7 / 2.9 057000A206           057000A304      ...(KA'S)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
1

ftt__ELGNI_@X@IEdE_ DEB 1 h _GQNISQLu_@NQ_INSIBUdENI@IlgN                                     PAGE                  31 QUESTION     6.07           (1.50)
The Auxiliary Feedwater System receives an automatic start signal from the 2 out of 4 logic on low low S/G 1evel on "C" S/G. CA1A failed to start. What will be the position of following valves ONE (1) minute after CA1A not starting:
INDICATE OPEN OR CLOSE CA62A     CA58A         CAS4D CA46D     CA5C A        CA42B NOTE: SEE ATTACHED DWG ANSWER       6.07           (1.50)
CA62A -c1 c re CA58A c 1 =c     ofc4 o p e ,J CAS4B rJ eee-    apoa CA46B open CA50VA-: 1 car   o pc4 CA42B    open   (6 parts @ 0.25 ea.)
REFERENCE OP-CN-HO-CA Page 14 F.1.A                                                                                               ;
k/a 4.0 / 4.2        3.1 / 3.4 LPSO 7 061000K404      061000K406          ...(KA'5)
QUESTION     6.08           (1.00) l i
The Feed Pump Speed Controller maintains a programmed D/P signal thru a lag circuit.                                                                                            3 l>
LIST the TWO (2) major reasons for the delay circuit.
(

rl
                                                                                                    !f n'
T AIT UL XE  e I
L I
A R                                             s Y                s e                            e F                P                            P E                s                            A E.
D W
A               :
T E
R
(
C A
                           )
N       e                            %           C O               c, T
E S
a 6
M
:                 8
                                                                                             ^
W               V             v G
V G
G               C
:    D A             C A           a                   A C
s e
W           E
                                       /                                     #
R   I E    D N   .F   t b        e=                         :
Y
                       ' C J    N C T L 1- N R Y 5 C-                                T A / 9 F                                 D I                                       P N C 2 C-I M         A N R           -
G           6 U l S
E   e      lDA T
O a           E.
N v.
L            3 Y
gu  n 7
8 6
e w                                          DsE$s O Qr         4    -1     l Il   II   ll1

                       &_EL89L@YSIEde_DESI@N _ggNIBQ62_8ND_JUSIBWENIOJ19N                    2         '                    PAGE 32 L %.                                     .;  .
                         . ANSWER:                6.08           ~(1.00)
:-1'. ' Allows flow control valve response prior to FWP speed change.. . (0. 5 ) .                                                                        1
:2. Filters out short term transients for.which a change in programmed dp-is not desired.                         (0.5)
                                 . REFERENCE
:OP-CN-HD-IWE Sec 2.2 A.1.c.
LPSO obj. 4 k/a 2.5 / 2.0 059000K405            ...(KA'S)
QUESTION . 6. 09 '                   (1I50)
                                  -Concerning Intermediate Range.(IR) Nuclear Inst.
                                 'a) What is "over-compensation", and doncribe the detector operation in this condidion.
b).If an IR Detector is "over-compensated", would incicated
                                         . power be (higher or lower) than actual power?

6t__E68dI_EX9IEd3_QEglGN,_CQNISQ6t_8NQ_INGIBUdENIGIlgN i                                          PAGE                      33 ANSWER                6.09         (1.50) a) "Over-compensation" is the condition in which toe much gamma compensation voltage is applied. (0.Q) The gamma signal f rom the inner chamber is greater than the gamma signal from the outer volume (0.'L) such that some of the neutron signal is cancelled along with the gamma signal from the outer chamber. (.y)
NOTE: Similar wording expressing the above concept accepted, b) Lower      (0,5) 1 REFERENCE OP-CN-HO-ENB LPSD obj. G k/a 2.7 / 2.9 015000K502         ...(KA'S)
QUESTION             6.10          (1.50)
A reactor trip occurs from 100% steady state power conditions. The B Reactor Trip Breaker did not open.
Concerning the Steam Dump System.
a) What is the maximum number of banks of steam dumps that could receive an open signal.
b) What will the post trip Tave be assuming no failure other than B reactor trip breaker not opening.
c) At what (Tave-Tref) will bank one (1) be f ully open?

                                                                                                         ,\
p
         ?6t __eLeNI_gygIgd@_QE$1@Nu_Q9NIBQ6t_8NQ_lNSIBydENIGIlgN                               PAGE 34    !
l l
   .                .                                                                                      l
   \.
        - ANSWER            6.10            (1.50) 1.
a) all five (5)                      (0.5) b) 560 deg. F (557 + 3) (0.5) c) 5.8 deg. F          2.  . 'l      (0.5) n 6,6 t .7        /h.s c o ca [eno 4r"c7c.~$sekro   l 75"/    # # 'i ~ 3 * # 7b 4*4 d 3 '# = 4, f REFERENCE OP-CN-SYS-STM-IDE 1
LPSD obj. 4
           ~k/a-3.5 / 3.6             3.7 / 3.9 041020K105             041020K417          ...(KA*S) 1
         - QUESTION .6.11                   (2.00)
In the Rod Control System, " bank overlap" exists while operating in both auto and manual. Overlap occurs at 115 steps, a) How AND where can the " bank overlap" setpoint be changed?
b) .How AND where can the " total" BOU count be manually increased'or decreased?
ANSWER            6.11            (2.00) a) By adjustment of the thumb wheels for each bank (0.5) in the BOU in the logic cabinet. (0,5) b) By the + or - push buttons (0.5) for the BOU in the logic cabinet. (0.5)
REFERENCE
           'OP-CN-HO-IRE page 11 & 12 of 22 LPSO 3 & 4 k/a 3.5 / 3.8 OO1000K403              ...(KA'S)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

1:v
:                                                         z                                PAGE- 35.
(6z__ELONI_gygIgdg_QEgigN_CQUIBQ62_6NQ_INSIBQUENIGIlON O'
! 'y a                   .
[.
I l        QUESTI'ON: -6.12.                              (2.00) l' An Urgent Alarm is received'on Power Cabinet 2AC.                       LIST.FIVE'
                        ~
           . ( 5 ),                 causes of an Urgent Failure Alarm in a Power Cabinet.
        . ANSWER.-                        6.12          (2.00)
          "a)'1.'                     Regulation failure
: 2.          Phase f ailure -
                          -3.-Logic error.
: 4.          Multiplexing error
: 5.         Loose or missing circuit card. (5 3 0.4 ea.)
REFERENCE 1 OP-CN-HO-IRE- page 14 84 16 of 22 LPSO obj 10 k/a.3.5 / 3.8-                          3.7 / 3.9   3.4 / 3.8 OO1000K403                            OO1050A201       OO1050K401 ...(KA*S)
QUESTION                          6.13         .(1.75)
The Power Mismatch circuit in the Reactor Control System has TWO'(2) gain units. 1 State'the purpose AND function of'each of these gain: units.

6.t__ELONI_QYSIEMS_QEglGNu_QQNIBQ6t_8NQ_INSIBUMENI@IlgN                                                                                      PAGE           36 a       8 1                                1.50 ANSWER        6.13 (1[)
The Non-linear (gain unit) U.25) - converts the power mismatch signal to an equivalent temperature error signal.
(0.25) (The larger load changes the larger the effect.) The low and higg' gains are variable according to power mismatch (p wi2Jr'. Increasing the gain for a range of mismatches increases the initial output of the channel initiating rod motion more quickly. (0.25) l' The variable (gain unit) 44'~4Mdr - Minimine overshoot on large power changes. (0.25)                           Reactivity changes at low power levels _have a smaller effect on the rate of thermal power lev.ls than reactivity changes at higher power
          -levelse _/h"d This variable gain enables the mismatch channel to provide adequate control at low power levels, as well as stable operation at high power levels.                                                                      (0.25)
REASONABLE WORDING ACCEPTED REFERENCE OP-CN-HO-IRX LPSO obj. 7 k/a 3.8 / 3.8       3.2 / 3.3 001000G007         OO1000K402                             ...(KA'S)
OUESTION      6.14         ( .75)
T-HOT in loop C fails high. The Delta T Def eat Switch on MC10 is selected to defeat loop C delta T.                                       What is the function of the Delta T Defeat Switch?

6-                      ELONI_SYSIEd@ _QE glG N t _C QUISQ6 t _8NQ_IN@ISU t1ENIGIlQN    PAGE 37
: p.                                                  .
   . ~.:                                            .
g I
ANSWER                         6.14                             ( .75)
                                 .a)'The switch ~ defeats the Delta T for loop C input to the
                                                    ' rod insertion limits. -(0.75)
: REFERENCE OP--CN-HO- I P X LPSO'obj. 8 k/a 3.7 / 3.8
,                                      012000K10                       ...(KA'S)'
l l
QUESTION- 6.15                                                   ( 1. 00 )'
A."NOT P-10" bypass switch has been added to the SSPS.
If the "Not P-10" Switch is placed in'the bypass position, State the coincide,that is required to trip P-10.
rK8 ANSWER                         6.15                              (1.00)
                                   '2 out of 3' operable channels. (1.0)
REFERENCE
                                   'OP-CN-HO-IPX                     3 r F O* ) #
LPSO.obj.-8:
                                  .k/a 3.6 / 3.6
_012000G007-                          ...(KA'5)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
j

E, hi__E 68 NIL EYSIGda_ DE S19Ni_ G 9 NIB 961_8ND_INSIBLJUENIBIIO N                         PAGE 38 l-l..
         'OUESTION .6.16-             (3.00) iThe RN System is normally aligned to Lake Wylie.
     ,     -a) STATE 'the TWO (2) conditions that will automatically align to the-RN System to the Standby Nuclear Service Water Pond (SNSWP).
b)1Using the attached drawing of'the RN System, circle EACH Lvalve.that-receives an: automatic signal in.the switch over on LOW-LOW PIT LEVEL from Lake Wylie to the SNSWP, AND
                -indicate whether it is an open or closed' signal.
ANSWER        ~6.16        ' (3. 00) a) 1. ASP transfer. (0.3) 2.1 Emergency low level-in either pumphouse pit. (0.3)
           ~b) See attached. drawing. Each valve position is worth.(0.1)
REFERENCE OP-CN-HO-RN page 19 d.4;and-page 35 2.5 A.1 LPSO obj. 8 k 18 k/a 2.8 / 3.2 076000K406         ...(KA'S)
          -QUESTION- '6.17             (1.00)
Assuming the diesel generator is tied to the bus, EXPLAIN what will happen if the sequencer reset button is depressed while sequencing is-in progress during a blackout.
j
* e 3                      . 6 9
4b      l
                                               ,              w S                                                              Y
                                                      -"--        3'
                                               '                                     )
7        !!    jyi
                                                 =
                                                 =
i-     !s    v s
g
:r-                       ki                           Xi U
o      e hhY                           ihI                _
h                          =    ,
g e
[        M       gi                 -          gg                                                    1    _
E    i        5    i          E   i                                           '
                                                                                                                                                    !~
I                     X,                           Xe,   _
                                                                                                                @ -w-a it     il i                                                      -
I                          hh5                      h                         N s    e      i o                             I                           XI
_r 4
W                       !y          13   -w-i                        =                3
                                                     -v           tu
                                                                             'i                 n--
b    h 1
481 On hjh

C.
             ~
    $                 ,r r
t e
d"-
gM
                                   @            @s Er3 l
G.
b4  s Xl a
a g,'
m, s
a_
a d               n            m e
o                       a o
tI            s a
a
                                                             ,_               n                                       _
m o
h                         &                      '
                     .r s-h
                                                                                                             =
s.
s u2 h                         @          l (j      '
            ^                                .
v                      O'&I            ;
n
                           ..             " ..                                                        s      .-
     )                                           a           f,   '
* s     ,                     e I
_        "       e e
* m UO c     -    VM v                        V&E i
Q9&
s 2 s
a8                                                       l E                                                                                     _
u 3-                        W                        "
s s                                                   s                                                           _
Q C                                                                                                      -
N g                                                                L o'
R T
R g A y N
g             g        '
{m 1
                                                                                                               $~
N g N
G 9
1 c
P
                                                      .                    gl                                  [
m U ln S
E     n      l AWN u           "
O                 "
N W
1 2
(o. c 8
ki V
2                                                                             /   /
9                                                                            f o    E  '
2c 8                                                                                 $             o b            7                                                                                 /
                                                                                                        //
                                                                                                        # /
C' J)                                                                                             /
C
* 2 v/

6___E60NI_SYSIEMS_ DESIGN 1_CgNIBg62_ Gyp _INSIBUMEUIGI1ON                                                                 PAGE               39                i
(
l
  -     .                                                                                                                                                          l ANSWER      6.17            (1.00)
No f urther load groups will be applied.        (1.0)                                                                                                         .
REFERENCE MNS EDG load seq. lesson plan p 14 CNS PSM CN Sys EQB k/a 3.5 / 4.0 064000K410         ...(KA'S)
QUESTION    6.18            (1.00)
Concerning the Ice Condenser System, answer the following questions.
a) The stored ice having a baron concentration of at least
_______ ppm,      ., ____________ and a pH of ,_______
to ________.
b) WHY is the ice solution maintained with a specific ph?
ANSWER      6.18            (1.00)                               7[                                                                      g
                      .\2 6                              .' W    9p q* 9, f _ ~a~ "4 "
a) 1800 ppm ( 0.,25 ) of sodium tetraborate ( 0.25)       i b) Enhances iodine absorption. (                4)
OA fph for corrosion contrel f chT gy, f ,
REFERENCE DP-CN-HD-NF page O LPSO obj. 5 h/a 2.8 / 4.3       3.5 / 4.3 025000 GOO 6       025000G011         ...(KA*S)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

     $z__ELONIMSIEMS_ DESIGN,_c9 NIB 962_8ND_INSIBLJtLENIGIlgN                                                                                                                                                                                                                  PAGE -40.
     . QUESTION: 6.19                                                             (1.00)
A low-lowL-level.in.the Ice Condenser glycol system eApansion tank will close the supply. and return outside contaimnent isolations.
HOW would you open the -valves with the low-low level tconditionsin the expansion tank?
ANSWER.          6.'19                                                     (1.00)
:A. key bypass' switch (0.5)'on a local panel. (0,5)
REFERENCE OP.-CN-HO-NF page 15                                                           E.1.a.1 LPSD ob.). 4 k/a 2;2 / 2.5                             4.0 / 4.0 025000 GOO 9-           025000K401                                                                                                                                  ...(KA'S)
      ' QUESTION        6.20                                                       (2.50)
Concerning EMF-35 Unit Vent Particulate ( L8<H) , EMF-36 Unit Vent ~ Gaseous ( L84H) , EMF-37 Unit vent iodine.
a) LIST the FOUR (4) auto functions associated with a " Trip 2" alarm.
b). In checking the alarm you, took the filter-tape.to the.
fast' position, then to the " Program" position. What does the. Filter tape do in the " Program" position.
L-                    -  _ ___   _ - _ _ _ _ _ _ - _ - _ _ _ _ - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

6 3__e!=eNI_gygIgtLS_pgSIGth_C9 NIB 961_0Np_JNSIB!LMENI@Ilgd                                                                                PAGE   41 l..
ANSWER             6.20         (2.50) a) 1.-Stops.VA filtered and unfiltered exhattst fans                                                                          Ay b!oj Vf*   '
: 2. Stops VF   exhaust fans  Ar             /              On                                         l   . Ve~t -
e
              ' 3. Secures WG release (shuts WG-160) Ooscou3 (da.s e t .
: 4. Secures cent air release (shuts VQ10)                                                                                                 ;
(4 parts G) 0.5 ca.)
      ' b) Tape stationary (f or 30 mind then advances (17 in. / min.)
until clean tape positioned for sampling.                                                                                                  <
l'   ' REFERENCE
     ^OP-CN-HO-EMF page 11;?x 14'                                                                                                                          l LPSO obj. 3
      .k/a 4.0 / 4.3            2.9 /.3.0
      -073OOOGOO7               073OOOK401     ...(KA'S) l
(***** END OF CATEGORY 06 *****)
: 7.                      PROCEDURES - NORMAL3 _8BN9Rd8Lx_EMEBQENgy;AND-                                                                        PAGE 42 RADIOLOGIg86_ggNTRQL
~
i QUESTION. 7.01                                                               (1.00)
L ..
SC'ENARIO:
Catawba Unit One (1) is in Hot Standby and preparations are being made to startup. . As the Shift Supervisor you are given the f ollowing Steam Generator "B" chemistry parameters:
Chlorides =                                     20 ppb             pH = 9.3           -Silicates =       299.0 ppb' Sodium                                       =  19 ppb             Cation-Conductivity'= 2.2 umho/cm
[                                  Sulfates                                     =  21 ppb             Dissolved Oxygen                    = 4.9 ppb NOTE: Attachments.7-1 through 7-5 are attached for reference and data placement.
t         From the following, SELECT the most appropriate action:
a)      Proceed w/ plant startup; return any "out of
=
spec"' parameters to normal power operation values prior to exceeding a power level of 30 percent.
b)      Proceed with~ plant startup; return any "out of specification" parameters to normal values prior tol exceeding a power level of FIVE (5) percent.
c)      Proceed with "Out-of-Specification Action Level DNE                                 (1)"' steps prior to conducting the star tup.
d)      Proceed with "Out-of-Specification Action Level TWO (2)" steps prior-to conducting the startup.
l ANSWER                           7.01                                        (1.00) b)                        (1.0)
REFERENCE T&Q CD-SOO20, Element #2; Catawba LP OP-CN-HO-SC; Pgs 11-12; LPSO Objectivo 5; Catawba Abncrmal Procedure AP/0/A/5500/34 KAIR 2.5/2.9 194001A114                                                           ...(KA'S)
(*****           CATEGORY 07 CONTINUED ON NEXT PAGE ****t)

      - _ _                          v----            --              .
CNS                      SECONDARY CHEMISTRY OUT OF                                                           PAof No.
,,          AP/0/A/5500/34                      SPECIFICATION                                                                         2 Retype e6 ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED C. IMMEDIATE ACTIONS NONE.
O. SUBSEQUENT ACTIONS NOTE         Action levels are numbered in order of increasing severity.
Action Level 1 is the least severe, Actron Level 3 the most severe.
: 1. Identify Required Action Level Referring To Enclosure 1.
CAUTION            in the event an out of specification secondary chemistry
                  *********          condition rapidly progresses from a less severe to e more severe Action Level, the requirements of the more severe Action Level should be immediately implemented.
: 2. Action Level 1.                           o      Go to Step 3.
: a.      Source of problem:                       a. Continue attempts to IDENTIFIED.                                    identify source of problem.
: b.      Attempt to correct source of problem.
: c.      Problem corrected within:                c. Go to Step 3.                                                  !
ONE (1) WEEK.
: d.      Go to Step 5.,                                                                                                l l
: 3. Action Level 2.                           o      Go to Step 4.
: a.      Request Chemistry verify s nple analysis,
: b. Check Power Level:                       b. Reduce power level to 1 301.                                         ! 301 within 4 hours.
NOTE         Reducing power to $ 30s will minimize corrosion AND maintain                                                  ,
sufficient flow to allow automatic Feedwater Control while                                                     !
attempting to correct the problem.                                                                             I
: c. Source of problem:                       c. Continue attempts to IDENTIFIED.                                     identify source of problem.
: d. Attempt to correct problem.
Page 2 of 6

vu--~---~-                 -
CNS                  SECONDARY CHEMISTRY OUT OF                           PAet wo.
 .  . AP/0/A/5500/34                    SPECIFICATION                                         3 Retype #6 ACTH3N4XPECTED REsM)NSE                       RENSE NOT OSTAINED
: e. Problem corrected within:             e. Go to Step 4.
100 HOURS.           ,
: f. Go to Step 5.
: 4. Action Level 3.
: a. Request Chemistry verify                 #
sample analysis.
NOTE     Reducing power level to < h within 4 hours will prevent rapid S/G corrosion AND minimize secondary plant contamination.
NOTE     in the following step (s), plant operation will be con @Jcted so that maximum blowdown flow can be attained while minimizing S/G steaming. This may be accomplished by utilizing decay heat OR,    _
maintaining power at a level so that cooldown does not occur with maximum blowdown flow and little or no decay heat.
: b. Ensure power level reduced to < h within 4 hours.
NOTE     Further Power Reduction OR plant shutdown may be necessary to prevent additional secondary plant contamination.
: c. Request Chemistry Department recommendation AND concurrence for continued plant operation.
: d. Source of problem:                    d. Continue attempts to identify IDENTIFIED                                   source of problem.
: 6. Correct source of problem.
: f. Restore Secondary Chemistry Parameters to normal values by:
: 1)    Feed AND blood 0
1
: 2)    Drain AND refill as app %priate.
Page 3 of 6 Gaedion   301

         . - _ _                                   u,.     ..         .-
       .              CNS                     SECONDARY CHEMISTRY OUT OF                        'AG8 W-
_ ,. .         AP/0/A/5500/34                    SPECIFICATION                                     4 Retype #6 ACTION /tXPECTED RESPONSE              -
RESPOftSE NOT OSTAINED
: 5. Evaluate Plant Status:
o    JF, power reduction required to comply with Action Level while in this procedure, THEN consult plant Engineering / Chemistry staff prior to any power ascension.
                                                              -END-l l
1 l
l l
l 1
I l
Page 4 of 6 1
Quedien M                                                j

f/7/ l/ U UT/L5 (/Lf v v vl5Mu V
l
* CNS              SECONDARY CHEMISTRY OUT OF SPECIFICATION i
AP/0/A/5500/34                            ENCLOSURE 1                                             5 Retype #6 l
l l
l Listed below are the normal AND Out of Specification values for Monitored Secondary Chemistry Parameters.          Required Secondary Chemistry Parameter Values i
vary with the existing mode of plant operation. Listed parameter values are based on S/G Owner's Group Secondary Water Chemistry Guidelines. Required Action Levels for Out of Specification conditions are identified.
A. Mode 1 (Power Operation):                                 ,.
: 1. S/G Blowdown Samples (S/G A, B, C, D):
(Prior To            Out of Specification Values Pa rameter       No_rmal Value             Power                       Action Level:
Escalation >30%)            1           2          3 pH            8.5 - 9.4               8.5 - 9.4          < 8.5 - > 9.4 Cation Cond, umho/cm          1 0.8                    ($ 0.8)           > 0.8          >2       >7 Na, ppb           $ 20                     ($ 20)            > 20           > 100    > 500 C1' ppb           $ 20                     ($ 20)            > 20           > 100 SiO2, ppb         $ 300                    ($ 300)           > 300
             ~
SO 2, ppb         $ 20                     ($ 20)            > 20 4
: 2. Final Feedwater Sample:
Out of Specification Values Parameter                    Normal Value                              Action Level:
1           2          3 pH                       8.8 - 9.4                        < 8.8
                                                                        > 9.4 Dissolved 02, ppb            $5                               >5 Total Copper, ppb            $2                                '2 Total Iron, ppb              $ 20                              > 20 N H , ppb                    > 20                              < 20 24
: 3. Hotwell Pump Discharge Sample:
(Prior To             Out of Specification Values Parameter        Normal Value              Power                       Action Level:
Escalation >30%)              1          2          3 Dissolved 02, ppb              $ 10                        ($ 10)            > 10          > 30 Page 5 of 6 Quediow lot

                                                              ,,,wun g ,v ,                 . v
  .                                 CNS                SECONDARY CHEMISTRY OUT OF SPECIFICATION AP/0/A/5500/34                          ENCLOSURE 1                                          6 Retype #6 l
B. Mode 2 (Startup) AND Mode 3 (Hot Standby). AND Mode 4 (Hot Shutdown):
: 1.       S/G Blowdown Samples (S/G A, B, C, D):
Parameter                     Normal Value (Prior To Power Escalation >5%)
pH                        8.5    9.4                                                 ,
1 Cat. Cond. -mho/cm             < 2.0                (< 2.0)
                                                                                         ~
Dissolved 02, ppb              35 Na', ppb                       $ 100                (1 100)
C1', ppb                       $ 100                (1 100)
S0 2, ppb                      5 100                ($ 100) 4 7        Final Feedwater Sample:
Parameter                     Norn. i Value Dissolved 02, ppb             < 100
                                   . N2H4, ppb                    33x(02)
C. Mode 5 (Cold Shutdown Wet Layup):
: 1.      S/G Blowdown Samples (S/G A, B, C, 0):
Parameter                    Normal Value (Prior To Heatup) pH                 9.8 - 10.5      (8.5 - 9.4)
N2H4, ppm                 75 - 200 Sodium, ppb              < 1000          6 100)
C1 , ppb
                                          ~
i1000           {}100)
S0 2, ppb                $ 1000          e 100) 4
: 2.      S/G Fill Source:                                                                 l l
Parameter                     Normal Value Dissolved 02, ppb              5100 in fill                > 100 in fill - Do NOT use as source Page 6 of 6 Que34(on MI

(i                           .
Zz__BBOCEDURES - NORMAll_ABNQRd8Li_gMgBQgNgY_8ND                                                                                                                                                PAGE      43
                           - 80DJQLgg1Q86_ggNISQL r,
I,'
         .s:                 .
JOUESTION                                            7.02                                          (1.00)
               ' Which' of ' the f ollowing - statements, concerning Component-Cooling Water System..(KC) Operation (Loss of KC)-is TRUE7:
a ) ': -If' KC and-~NV Seal Cooling for ANY Reactor Coolant (NC)
Pump is lost, then - within TEN-(10) minutes --NCP Eeal Injection Flow (f rom the SSF) - must be initiated.
                         'b)-Upon a' loss ofLKC,'if NO KC pumps can be started, the reactor and all but the NCP with the LOWEST Seal Outlet and Lower Bearing Temperature must be tripped.
c);.Upon a loss of.KC,'if either " Surge Tank LO-LO Level''
                               --alarm is lit,.the Non-Essential Header Isolation Valves auto-OPEN and all but'ONE'(1) KC pump must-be secured.
ANSW2R                                             7.02                                         . ( 1. 00) a)            (1.0)
REFERENCE Catawba LP:OP-CN-HO-KC;.~Pgs 7-8.and 12-13; LPSD Objectives 9 and 10p Catawba-Abnormal Procedure AP/1/A/5500/21 KAIR 4.0/4.2                                                                    3.4/3.5
  .-4; OOOO26K303.                                                                  OOBOOOK301                                 ...(KA'S) f
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
s        - _ _ _ . _ . _ _ _ _ _ _ . - _ _ _ . _ _ _ _ . _ . _ . _

12t__EBOCEDURES --NORMAL iGBNQBMG61_EMESQgNgy_GNp        i                               .           PAGE 44 tB8D196991986_99 NIB 96 QUESTION L7.03                                        (1.00)
The following " NOTES" appear within procedure OP/0/B/6500/14; " Operations Li quid Waste Release":
l                                                    "To adjust the (Conventional Low Pressure Service                I L                                                    Water) RL setpoint, pull out the. flow gauge and                 l l                                                    move the pl astic gears by hand until the desired                l l                                                    setpoint is reached.          The highest discharge rato         j should be- used f or releases (normally 100 gpm).                l The vclue for minimum RL flow must be less than or               i equal to the actual RL flow."
                                                     "If RL flow drops below this setpoint, it will                   j auto close 1WL-124 and terminate the LWR".                       l IF the RL flow meter proved to be. inoperable, which of the                                               ;
f ollowing. actions is appropriate / correct, . as per procedure                                          j OP/0/B/6500/14 and Unit Technical Specifications:                                                         l a) Set RL~ Discharge. Flow setpoint to MAX value L(overrides                                l interlock w/ "WMT Rad Monitor Outlet" (1WL-124)J - Log acticns on LWR Form - Proceed w/ LWR dischar.go - Stop                I LWR discharge if "RL DISCHARGE LO FLOW" is receivod.
b) Set RL Disch Flow setpoint to MINIMUM (which overrides                                    ,
interik.w/ 1WL-124) - Log actions on LWR Form - Proceed               l w/ LWR discharge - Monitor RL Discharge - Stop LWR                    l
                                               'disch if.RL flow drops below that needed for discharge.               j c) Declare channel INOPERABLE - Set RL Disch Flow setpoint to' MAX value (this overrides 1WL-124 interlock) - Log                 l actions on LWR Form - Open WMT Outlet (1WL-124) Bypass Valve 1WL-744 - Proceed with LWR discharge, d) Place switch l abell ed "RL Disch Flow to WMT Rad Monitor Outlet" to BYPASS / TRIP position (this prevents signal input) - Log actions - Monitor RL Fl ow - Stop LWR discharge upon receipt of "RL DISCH HIGH FLOW" alarm.

E ?Zi__EBQGEDUBEE_:_NQBdQLt;6@UQBd@bt_[1EBQgGGY_8ND                                                                                                                                'PAGE 45 BBD196001GGL_GQNIBg('
,33 ox
         ~ ANSWER                                                      7.03                                     : ( 1. 00)
           'b)                                 (1.0)
LREFERENCE
  ,         .T&Q.CO-ROO45, Elements #2 and 6; Catawba LP-OP-CN-HO-WL; L'           Pgs'20-23; LPSO Objectivec 4 and 11; Catawba Operations
           . Procedure OP/0/B/6500/14, Enclosure 4.1 and Annunciator Response Procedure OP/1/A/6100/10M, Panel 1AD-12 l'
KAIR 3.1/3.8
           -000059G005                                                                                     ...(KA's)
QUESTION                                                    7,04'                                     ( 1 '. 00 )
According to procedure AP/1/A/5500/11 (CASE II); "PZR Spray Control Valve Failure"; which ONE (1) of the following sets of. actions should be taken if a PZR spray valve f ails OPEN and CANNOT be closed?
NOTE : Assume that PZR-heater operation IS NOT sufficient to maintain NC system' pressure greater than 1945 PSIG.
a) Lower plant ' power to less than 46 percent (PS)'-. Secure NCP associated w/ affected. spray valve ~(1A for 1NC-27; L                                             1B f or 1NC Manually isolate spray line by shutting
                                           -isolation valve (1NC-27B-for 27A; 1NC-298 for 29A) b) Conduct- Unit Shutdown as per OP/1/A/6100/02 - Take Rod Control to Manual - Attempt to raise-T-ave - Maintain T-ave 'FIVE (5) degrees greater than T-ref - Deenergize power supply to affected spray valve c) TRIP REACTOR - Secure NCP associated w/ affected spray valve-(1A for 1NC-27; 1B for 1NC-29) - Go to EP/1/A/5000/01; " Reactor Trip or Saf ety Injection" d) INITIATE SAFETY INJECTION - Secure NC pumps - Go to EP/1/A/5000/01; " Reactor Trip or Safety Injection"
         ' ANSWER-                                                      7.04                                      (1.00) c)                                (1.0)
REFERENCE T&D CD-ROOO3, Elements #5 and 6; Catawba LP OP-CN-PS-IPE; LPSO Objective 9; Abn Operating Procedure AP/1/A/5500/11

Zu__EBOCEDUBEg_ _NOBd86t_ODNQBd8(t_EMEBGENgy_GNQ                                                                                                                                                                                                               PAGE                                    46 8891060 GIG 86_G9 NIB 96 KAIR       3.7/4.1 OOOO27K303                                                                                         ...(KA'S)
DUESTION                    7.05                                                                                                                                     (1.00)
The reactor operator inf orms you that P/R channe) 42 is reading *110 percent power, I/R channel 35
* d(-)4 amps and I/R channel 36                                                                                                                                                  *6E(-)4 amp. All other  /R channels are reading-(as an average) ~101.6 percent pop r.
LAs the shi f t supervi sor your most corr                                                                                                                                              t response is to:
a) Verify Trip NOT required - Check T.S. Computer /CSF -
reduce power to ~100.0 p- n t - continue operations -
ensure P/R and I/R ch,.                                                                                                                                            ea calibrated - conduct OPTR.
b) Believe indication o- High Power - note I/R channels equal to *110 pepc' t P/R - note 3/4 coincidence met -
order R                                                                                                                  '
Ig/EP/1/A/5000/01 "Rx Trip or SI".
c) Note I/R c on el indication NORMAL for *101.6 percent power - mai                                                                                                                  ain current power I v1 - commence correct-ive action IAW AP/1/A/5500/16; "P/R Malfunction".
d)    Notp/possible DROPPED ROD and I/R channels INCORRECT -
noffe P/R channel 42 CORRECT - verify dropped rod and shift - commence actions for dropped rod
              /rciated flux and AP/1/A/5500/16 CASE III; "I/R Mal f uncti on" .
ANSWER                        7.05                                                                                                                                    (1.00) a)       (1.0)
REFERENCE T&O CD-ROOO8, Elements #1 and 3; T&Q CD-SOO34, Elements #1 and 3; Catawba LP OP-CN-HO-END; LPSO Objectives 11 and 12; Abn Operating Procedure AP/1/A/5500/16; Emergency Procedure EP/1/A/5000/02 KAIR 3.6/3.9 3.0/3.5 3.3/3.6 OOOO33A201                                                                                        OOOO33K302                                                                 000033202      ...(KA'S)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

       !Z1__EBggEpgBES_ _NgBd86t_GDNgBdGLi_gdEBgENgy_8ND.                                       PAGE   47 88D196991986_99 NIB 96-qp           .
1 J
       ? QUESTION         7.06-       (1.00)                                                                j
        -The unit-has a known primary-to-secondary leak.
LWhich ONE -(1) , of the following sets of conditiens, would
                                                                  ~
: require.the shift supervisor to transition'from guidance as
        , presented.in AP/1/A/5500/10, " Reactor Cool ant . Leak (S/G Tube Leak)" to that presented in EP/1/A/5000/01,." Reactor Trip or SI"'and EP/1/A/5000/1E, "S/G Tubo Rupture"?:                                                     )
a) PZR-Iv1 less than program'Iv1     '
                                                      - NV letdown flow reduced I
to 45 GPM - ONE,(1) NV centrifugal pump at MAX output; suction from VCT     PZR Iv1. continues to slowly DECREASE
:b) PZR.1vl'less than 17 percent - NV letdown flow isolated
                     - ONE (1)' NV centrif ugal pump at MAX output;. suction from FWST - PZR lvl continues to' slowly DECREASE c)"PZR'Iv1 less than program,. greater than 17 percent - NV letdown flow at 45 GPM - TWO (2) NV pumps at MAX output suction :f rom' FWST - PZR lvl continues to slowly DECREASE                            ;
             .d) PZR Iv1 less. than 17 percent - NV letdown' flow isolated                                  !
                     - TWO (2) NV pumps at MAX output - NV pump suction.from l-                   FWST - PZR lvl continues to slowly _ DECREASE                                          I i
ANSWER-          '7.06        (1.00)                                                                ;
L
;          d)        (1.0)                                                                                  j U       ; REFERENCE TbO- CO-ROOO9, Element #4; T&Q CD-ROOO7, Element #1 Catawba
         .LP OP-CN-HO-EP4; LPSO Objectives 1 and 2; Catawba LP                                            .i OP-CN-HD-AT; LPSD Objective 1; Abn Procedure AF'/1/A/5500/10,                                    I
           " Reactor Coolant Leak (S/G Tube Leak)"; Emergency Procedures EP/1/A/5000/01, " Reactor Trip or SI" and EP/1/A/5000/1E "S/G                                    <
Tube Rupture"                                                                                    i I          KAIR 3.7/4.0- 4.2/4.4 3.9/4.1                                                                   !
:          000037G011            OOOO37K305     OOOO37K307      ...(KA'S)                                   l l-1 i
i
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
I e__-______-______-

10 Zz__eBgCgguBgg_:_N9Bd8GtlGBU9Bd8Gi_gdgBgghgy_8Up                                                                                                                                                               PAGE. 48-188DI96991C06_999IB96 b        QUESTION                                                                 7.07         ('1 ; OO)
SCENARIO:.
E                                        'A' trip.of CFPT "A" andJthe. inability to start CFPT "B",
while at 45 percent power, has resulted in a Rx trip.
L                                         LUpon auto sta"t of'the CA p' umps, water hammer effects E                                         :have caused a loss of CA pump B and apparent rupturing of. CA pump B discharge to the associ ated steam generator supply lines.
Even.with the turbine driven CA pump in operation, MAXIMUM CA. Flow to'all S/G's is LESS THAN 400 GPM.
          .In~ order to meet " intended" AP/1/A/5500/06 immediate actions;." Loss of-CF Supply to S/G's", the operator shall first " Check Reactor power less'than FIVE (5) percent, THEN:
[
a) Align valves -to isolate f eed . to S/G's " A" and "B"                                                                                                   -
ver.ify total-flow to S/G's "C" &'"D" is greater then 450 GPM - verify W/R levels are increasing
              -b) Align turbine driven pump to provide f eed to S/G's "C" and '"D"                               - verify total CA flow to S/G's is greater than 450 GPM c) Align valves to isol ate f eed to S/G's "C" and "D"                                                                                                      -
verify total CA flow to S/G's "A" and "B" is greater
                                            -than 450 GPM                                     -verif y' W/R levels increasing d) . Align turbine driven pump to provide feed to S/G's "A" and'"D" - verify' total CA flow to S/G's is greater than 450 GPM
        -ANSWER                                                                   7.07         (1.00) c)                                       (1.0)
REFERENCE T&Q CD-ROOOB, Element #10; T&O CD-SOO34, Element #10; LCatawba LP OP-CN-HO-CA; Pgs 9-15; LPSD Objectives 3 and 7; Catawba LP OP-CN-HO-AT; LPSD Objectives Sc and Sc; Abn Procedure AP/1/A/5500/06, " Loss of CF Supply To S/G's";
Emer Procedure EP/1/A/5000/2C1, " Loss of Sec Heat Sink" KAIR -3.8/4.1 4.4/4.6 4.0/4.3 OOOO54A204                                                                    OOOO54K303       OOOO54K304                   ...(KA'S)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

,,    7 &__EBOCEDURES - NORMAlt_QBNQBM8L _EMESQENQY_8ND t                                             -PAGE  49 L.             802106901C86_CONIB06
/-          s
   's
 ^
L     QUESTION        7.08         (1.00)
SCENARIO:
While the unit'is operating at'100 percent power a steam.line break / rupture occurs along.the main steam system .(.SM)1 equali z ati on header.
Safety injection (SI) andfmain steam isolation signals E                are generated and all main steam isolation 'v alves -
EXCEPT.1SM-3 (S/G 1C MSIV) - have closed in response to the ~ SM isolation- signal .
       'The failure of this MSIV to close. creates further problems, in.that ECHOOSE ONE (1)]
a)    The loss of'the: isolation safety function for the containment / reactor creates a potential for                                                 1 f ailure to limit the release of radioactivity.
                    ~
                -b)   -The associated' blowdown of the 1C S/G creates a large positive' reactivity addition to the core and extreme pressure rise within containment.
c)    The low (possibly=non-existent) S/G water level               -
i.e.; a loss'of. secondary inventory - presents
                       " dry-S/G" and-subsequent loss of NC flow due to voiding in.the loop.
d)    The rapid NC cooldown/depressurization followed by NC repressurination - by an SI - presents a number of " PTS"/" Failure of Vessel Integrity" si t uat i on s.
ANSWER          7.08         (1.00) d)       (1.0)
REFERENCE T&O CO-SOO34, Elements #10 and 15; Catawba LP OP-CN-HO-PTS; Pgs 12-14; LPSD Objectives 17 and 18; Emergency Procedures EP/1/A/5000/2C1, " Loss of Sec Heat Sink"; EP/1/A/5000/2D1,
         " Imminent Pressurized Thermal Shock Conditions" KAIR      4.2/4.5    4.5/4.7 OOOO40K301           OOOO40K304          ...(KA'S)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
: y.                                     .
                                     .y;
     ?Zz__EBgggpuggS                                NORMAL1 _8BN9RMAL1 _gMgBggNQy_8ND.           PAGE   50 LBBDIOL991GBL_G9 NIB 96
[.           :.
     /OUESTI.ON                           7.09           (2.00) iThere are the: FOUR (4) activity limits that an item must (meetLto be:: considered " clean" and/or " unconditionally released"- (f rom a RestrictediControl Area) according to Health Physics-(Radiation Protection). Manual - SD 3.0.8
      ' FILL'IN THE' BLANKS
:(Values below'basedt upon "DPM per 100 square cm" of sample) e ad -               ' Loose surface = contamination shall not exceed' _______
DPM. Beta / Gamma b)                        Total surface contamination (fixed & loose) shall not l exceed _____DPM Beta / Gamma.
c)'                        Alpha radioactive contamination shall not exceed ______
DPM (loose)
       'd )
Alpha radioactive contamination shall not exceed _____
                           - DPM . (fixed)                                                                       1 l ANSWER                              7.09           (2.00)
       = a)I 1000
       'b) 5000 c)-                        20
      -d)                100              (4 part.@ 0.5 ea.)-
REFERENCE                                                                                               !
LT&Q CD-SOO10, Element #0; Catawba HP Manual;.SD 3.8.8 and 3.G.10 AND.HPJLP OP-CN-HO-HP, LPSD Objective 13 1
K/A 2'8/3.~4                 .
i 194001K103                                ...(KA'S) 1 k
I
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
i I

2 iZz__EB99EDUBES_i_NOBd86t_GENQBdS61_Edg89ENgy_8NQ                                                     PAGE 51 l RADIOLOGICAL _ggNTBQL1
: m. :         .-
V
          ; QUESTION               7.10-         - ( 1'. 50) .
Answerfthe following'TRUE or FALSEf- Concerning the.EP's and l : monitoring;ofJthe Critical Safety Functions:
r
           ,ca):              OnceLan1CSF~is entered, due to a RED or ORANGE
: condition,'and no other higher priority path is-encountered, .that CSFEis performed until' completion or h                             otherwise directed.
            ' b.)             If 'all- conditions are GREEN, when using the CSFST's, monitoring frequency:may be. reduced ~to between TEN ( 10 )'
;.                            to TWENTY.(20)' minutes.
            'c)              fif.Jany-dRANGE terminus is encountered, the Operator in NOT required to monitor the remaining trees.
m.
L~' ANSWER.                        7.10-         - ( 1. 50 )
a)           TRUE          (0,5)
L               b)            TRUE         (0.5)
             .c.             FALSE-        (O.5) i T&Q CD-SOO34,, Element.#2; Catawba LP OP-CN-HO-CSF; Pgs                                                  '
8-9; " Rules.of Usage" LPSO. Objective 1; Emergency Procedure-EP/1/A/5000/02, " Critical Safety Functions" KAIR y4.1/3.9.'3.1/3.4-k' 194001A102               .'194001A115          ...(KA'S)'
          ~ QUESTION               7.11           (1.25) u                                .
L               Given theJattached-graph, LABEL (LIST), on the "Y" axis, the millirem (mR) limits associated with point' number ONE (1)                                              1 f
L               through point' number-FIVEL(5)..
i, i
   ~
H                ,

[
i
                                                                                                                                                      )
f t
I. .-
l        .         .
RADIAT105 EIPOSURE CONTROL GUIOt C,. kt f                    . ......................                                ............
                              .<~~    . _ - _ .
(N aious WRC @arter!F Dese Limit)
E.ad ou Quarter A
p, e q
                                                    ..............................[......\
Administrettee Limit to Net 10CT320.10t(t)
Asy Deee Above his Laea fluet le Supported Dy W3C 6 rare pS
( e ~ ,t.:i,        .. ti..t>
ta .a
                                                                                                                                      %seter
                                                     . . . II*I'I'NIS FUI *.I*I $                 I)                       T                   k
(? ' 2-                                                                                   .
I
                                                                                                            '      g      l      g 0
                                                                                                            '             8       i l                      '
g I
                                                                                                            '       s I      l 8                                           i       i
()* Y i             ~              ,    ,    <     a     ;
8           g     4       ,      g l
s         a     e            1 l     g l      l                       I
                                                                  '          e      e     c e         ,
e            e     t                    I       l       I 4            e      i      i 3    i    e    ,      e
                                                                                                       '             '      '       I        '
e                                                                          12       13      16 6     S       6    7     8     9      10     18 l    2    3 CA1ZWDAA QUARTER (Vttts) i o

J
         , Zt;_E8QQgQpRES"-- NORMAL _GQNQBMGL                                                          t              _EMgBQgNQy_GNQ t                      -PAGE 52 88D196QQ1GGL_QQNIBQL.
     -s                      o' ANSWER                                                           J7.11                  (1.25)
                -Poi'nt #1 - 500 mrem                                                                     - ( O'. 25)
               ' Point'#2T- 1000' mrem                                                                     (0.25)
                'Po' int #3 -11250 mrom                                                                    (0.25)
              $ Point #4,                                                           :2500 mrem-            (0.25)
Point #5 - 3000 mrem                                                                     (0.25)
Attach 1 Catawba Drawing CN-RP-18 NOTE: CWF f or new limits
                ' REFERENCE
                'T&Q CD-SOO10, Element #4; Catawba LP OP-CN-HO-HP; Pgs'12-13; LPSD Objective 9; Catawba Station Directive 3.8.6 KAIR 2.8/3.4-194001K103.                                                            ...(KA'S)
QUESTION                                                            7.12                (1.50)
LIST SIX-(6) items - as' addressed in Station Diri-<ctive 3.8.1                                                    .
                   "ALARA Program Procedure" - which can be taken by Catawba personnel (i . e. ; thoce that are responsible for maintenance-
                . activities)'which meet the goals of ALARA.
l

                ?Zi__EB9GEQUBER_:_URBdGLt_GEU9Bd86t_EdEBgENGX_GND.                               PAGE 53 18891960 GIG 86_G901806-
              -ANSWER                    7.12          (1.50)
NOTE:
AnylSIX (6)1of the following NINE (9) actions - each worth
                          ;0.'25 points, aa)       Pre Plan Jobs b)       Use people who can do jobs most ef ficiently c)        Use lowest dose people with adequate experience d)       Comply with requirements of Radiation Work. Permit o)       Minimize spread of contamination f )'     .Di spose of waste properly g)       -Decrease time spent near rad sources h)        Increase distance from the source i)        Utilino.any shielding which is available REFERENCE
                          ~T&Q CO-50010, Element tti;. Catawba LP OP-CN-HO-HP; Pgs 16-17; LPSD Objective 17; Catawba Station Directive 3.8.1 KAIR. 3.3/3.5 194001K104                K
                                                ...(lA'S) l l
l l
l l
l l
l l
l
(*****   CATEGORY 07 CONTINUED DN NEXT PAGE *****)

    'Zz__EBgCEQQBE@_;_UQBd861_8DNQBd862_EMEBgENgy_8ND                                                                                                   PAGE 54 689106991986_C9 NIB 96 L    QUESTION                 7.13              (2.00) a)-                 Using the " Classification Of Emergency" procedure, RP/0/A/5000/01 Handout, CLASSIFY the following event:
During refueling, scaffolding - which was improperly moved over the area - is dropped then f alls into and around the core assemblies.
l l                              Some assemb1'ies may have been damaged.
The' reactor vessel flange inflatable seal is damaged and, in turn, the seal collapses.
Ref ueling Cavity level - as read on 1NCP52OO - is indicating.'93 percent and rapidly decreasing.
Spent Fuel Pool level - as read on 1KFP5120 - is indicating *38 feet and also decreasing.
Monitor 1 EMF 15 is alarming - indicates *2O mR/hr.
Monitors 1 EMF 17 and 42 are alarming and " auto" actuation of containment evacuation alarm has occurred.
Alarms are not yet present for 1 EMF 38, 39 and 40 but " count per minute" levels seem to be                                                                                        j increasing toward alarm levels.
b)                  LIST the immediate actions for your classification.
l 1
: 7.          PROCEDURES - NORdGLt_GB$gRdGLx_gdERGENgY_GND                                  PAGE 55 80R196QGICG6_GQNIBQL ANSWER                          7.13         (2.00) a)-     ALERT-(1.0)                        g (2, i;C T C.            ll^.LI :n d. L   (. 5) e n. i . tor event oeing 2-1'--!'t a u -"SiteAreaEmergency"[t.o}
ALERT classification determined using Event Number 4.1.9; RP/0/A/5000/01 Enclosure 4.1 1
                                       "Possible" - but NO " major" - damage to spent fuel has been observed.
Water level WILL NOT fall below the level of the reactor vessel flange and, therefore, it will not further fall below the level of the fuel.                       ,
b)-      IF the candidate has classified as an ALERT - only ONE (1) (the following) immediate action necessary:
                                   " Initially notify individuals / organizations"       (1.0)
IF the candidate has classified as Site Area Emergency
                   - following THREE (3) immediate actions are necessary:
                                   " Initially notify individuals / organizations" (0.33)
                                   " Conduct Offsite Protective Actions"                (0.33)
                                   " Conduct Onsite Protective Actions"                 (0.33)
REFERENCE T&D CD-RO111, Element #1; T&O CD-SOO26, Elements #2, 3, 6 and 8; Catawba LP OP-CN-HO-SEP; Pgs 8-10; LPSO Objective 1; Catawba Response Procedures RP/0/A/5000/01, RP/0/A/5000/03, RP/0/A/5000/04 KAIR' 3.1/4.4 194001A116                       ...(KA'S)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
w-_____-_-

Zt__EB99EQUBgS_r_UpBdG62_GBNQBdGL1_EMEBGENgy_GND                                     PAGE 56
                   .889196991986_99NIBQL
     ' QUESTION                  7.14             (2.00) a)'            LIST FOUR (4) basic steps taken by the reactor operator
                            '(RO) during a " source. check" of a unit rad monitor.                  l b)              LIST'FOUR (4) basic actions taken by the RO in response                 i I
to ' an abnormal condition being presented / displayed by a rad monitor'Ei.e.; list the actions taken in response to a RAD THREE (3) alarm].                                              !
I
     . ANSWER                    7.14             (2.00) a)              li    'N.,  iy ~ rower Di.'    1 ; ;;b + 14+           '^.20 t)RT         Position " Check Source / Operate / Trip Adjust" switc1           l to the " Check Source" position.                 (0. " d)
                       \f)        Verify meter needle swings upscale.              (O. 6
                                                                                        ,,I         ,
                   } p[           Return switch to " Operate" position.
(O.f6[           ;
                                                                                       .$A b)               1)   Verify. alarm condition.                         (0.25)
: 2)    Ensure auto functions (if applicable)            (0.25)           i
: 3)    Check activity levels at other corresponding points.                                          (0.25)
: 4)    Notify HP or radwaste chemistry personnel (as appropriate).                                    (0.25)
REFERENCE TSO CD-RO116, Elements #1C, 2C, 3C; Catawba LP OP-CN-HO-EMF; Pgs 19-20; LPSD Objectives 3 and 9; Operations Procedures OP/1/B/6100/10X, 10Y, 10Z, " Response Procedures 1-RAD-1 through 1-RAD-3" KAIR 3.4/3.6 3.1/3.5                                                                    i 000061A204                   000061K302             ...(KA'S)
                                                                                                    ?
l l
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

Zm__EBQCEDUBES_;_NgBM86t_6pNQSMOL2_gMESQENCY_9ND'                         PAGE 57
                   .S8D196991GG6_9991896 QUESTION   7.15          (1.00)
               -SCENARIO:
Tamper seals on a recently received new fuel. container are damaged. When dealing with this problem, as per AP/0/A/5500/33; " Damaged or Missing Tamper Seals on Special Nuclear Mat'l Shipments" - and after assessing container contents - it is noted that the assembly has been damaged and fuel may have been extracted.
Using the " Classification Of Emergency" procedure, RP/0/A/5000/01 Handout, classify the above scenario in terms of:
: 1)    The Event Name/ Number
: 2)    The Emergency Action Level ANSWER     7.15          (1.00)
: 1)    Event Number 4.1.7 - Fires and Security Actions
: 2)    Notification of Unusual Event
                                                                        '5 *~ 'M f " Y ' * "*
                            ' fan oNotA) Stwdj y tverr{ is *$sw ed, A W          i REFERENCE T&Q CD-SOOl6, Elements #1 and 2; Catawba LP OP-CN-HO-FHA; Pgs 34-35; LPSO Objectives 4D and 11; Operations Procedure OP/0/A/6550/15, " Receipt, Inspection and Storage of New Fuel; AP/0/A/5500/33; " Damaged or Missing Tamper Seals on Special Nuclear Material Shipments"; Response Procedure RP/0/A/5000/01, " Emergency Classification Determination"                        j KAIR 3.4/4.1 3.1/4.4                                                             j OOOO36A202        194001A116       ...(KA'S)
I 1
QUESTION   7.16          (1.50)
In accordance with EP/1/A/5000/01, " Reactor Trip or Safety                      (
Injection", what are the THREE (3) automatic Safety                              l Injection signals?                                                               !
(NOTE: Ir.clude in your answer any setpoints associated with these s'. gnal s. Coincidence IS NOT required)

     .7e__EBQCEDUREQ - NORMAL                                           . u_6DNQBM8km_gMEBGENGY_GNQ'            PAGE    58  ;
889196001G86_GQNISQL ll                                                                                                                          1
                                                                           .                                                 l (1.50) .
ANSWER-                              7.'16 a).                           PZR. pressure less than 1845 PSIG                                (0.5) b );                           S/G pressures less than.(= to) 725 PSIG                         (0. 5)'
        'c)-                           Containment Pressureigreater than (= to) 1.2 PSIG (0.5)
     , REFERENCE                                                                                                             .
!        T&Q CD-ROOO4, Element "*- P9tawba LP OP-CN-HO-ISE; Pgs                                                             I 14-15, LPSO Objective 4; Catawba LP OP-CN-HO-NI; Pg 11                                                             4
        ,LPSO Obj ective 8; Emergency Procedure, EP/1/A/5000/01 lKAIR- 4.5/4.8 OO6030A201-                                             ...(KA'S)                                                 q
      -QUESTION' 7.17                                                  (1.00)
SCENARIO:
                                       'During Mode ONE (1) operation, a control rod drive mechanism (CRDM) is ejected from the NC vessel head, becomes an internal missile harard and breeches the containment structure.-
Satisf actory operation all ESF/ECCS systems has occurred in. response.to the subsequent LOCA and NC inventory:is.being restored.
Tavg - as determinedsfrom available indications -
is approximately 210 degrees F.
Given that " symptoms" contained in Catawba's " Lass of Containment Integrity" procedure are. associated with and similiar to the Tech Specification Definition of
                                        " Containment Integrity"; which ONE (1) " symptom" - of
                                       'the:FIVE (5) which denote a LOSS of integrity - is appl.icable to the above scenario?
l

J UZi__EB9GgDQBES_ _NQBdGL2_GBNQBb861_EdESGENQY_GND:                                                                     PAGE    591 n~~
                       " 68D196991986_G9dIB96
         .ANSWERi                               ~ 7.' 17 s
                                                                .(1.00)~
Tho' Containment leakage rates are.no. longer within the limits of Technical Specification 3.6.1.2 (Containment
                              . Leakage Limits)                                                            ( 1. 0 )
a                  NOTE:-
Ref erences : made to . "other"' symptoms i s inappropri ate and should be Jjudged ' " incorrect" ~ since the loss of containment integrity can be directly attributable to no other symptom than " leakage" - the ONLY item truly "affected" is the SOLID SURFACE of the containment - a
           +                     " hole" was created'by.the missile (CRDM).
REFERENCE
       ,     -TLD CO-50026, Element #2; Catawba LP OP-CN-HO-CNT; Pgs 15 and-20; LPSO Objectives-4, 5, and 15; Abnormal Procedure q          AP/1/A/5500/24; Response Procedure RP/0/A/5000/01, Enclosure 4.1 and Technical Specification LCO/ Bases 3.6.1.1/3.6.1.1 ll -KAIR; -3.8/4.2                                     3.7/4.3- 3.1/4.4 000069A201                                  000069K301          194001A116     ...(KA'S)
  ;i.
QUESTION                             7.18            (2.00)
SCENARIO:
:CNS Unit One (1) is in the process of "detensioning" the reactor vessel head and THREE.(3)- of the steam generators.are being drained for maintenance,                                                               l
[
a)              .In-accordance with guidance contained in AP/1/A/5500/19
                                 " Loss of, Residual Heat Removal-(ND)", what TWO (2) methods of " alternate core' cooling" might be available during a-loss of ND7 b)              How might the bor on concentration (stability) change while awaiting these " alternate sources of core cooling"? ELIST TWO (2) possibilities]
l l
1 I

       ,                         I lZz__PB9GEDURES1a-N9Bd862_8DN9Bd86t_EdgB9 Edgy _8ND                                                           PAGE 60
  .w                  BOD 196991906_G9 NIB 96-
         $^          ''#-'
b,
         ! ANSWER T
7.18 T (2. 00).
t NOTE:
            .Anyfreference,Eby the candidate, to attempt to cooldown the core,4 solely,-as por guidance presented in emergency E o, . procedure EP/1/A/5000/2B3 " Saturated Core Cooling", should
            ~ result;in point deduction.                    Please note that-step ONE (1) in EP/1/A/5000/2B3 places reader into AP/1/A/5500/19.
   ,,,.a)                  1) . Attempt to establish natural circulation conditions by feeding at.least ONE (1) steam generator with the turbine driven' aux foedwater
                                   . pump and-by manually " dumping steam".                                  (0.5)
                           ')       Attempt to manually align NC' drainage flowpath 1
l(via excess letdown'or loop point drains),
p                                   manually align flowpath to NC via NV and then attempt to. gravi.ty' feed from the FWST.                                (0.5)
[
b);           Any 'TWO' (2)' of the- f ollowing '(Each worth 0.5 points)
: 1)       Stratification due to lack of'any cooling flow.
: 2)        " Plate-out" of baron in thermal " hot spot" areas.
3)-      temperature increase /donsity changes (NOTE: While this actually af f ects baron coef ficient, it, in turn, affects " stability" of the concentration.
            . REFERENCE T&Q CD-SOO34, Element #9;-~T&Q CD-ROOB5, Elements #2 and 3; T&Q CD-ROO10, Elements #2 and 3; T&Q-CO-ROOOB, Element #9; Catawba LP OP-CN-HO-ND; Pg 23; LPSO Objective 61;' Emergency Procedure EP/1/A/5000/2B3 3 Abn Procedure AP/1/A/5500/19 KAIR 3.9/4.3 3.1/3.4 3.9/4.1
            -OOOO25K101                      OOOO25K301      ;OOOO25K303                           ...(KA'S)
          -QUESTION                7.19           (1.00)
            'In accordance with EP/1/A/5000/1A1, " Natural Circulation Cooldown", preference should be given to start the "1B" NC pump first THEN "1A" NC pump.
What- i n ' the basis f or this action?
u    1____       _

         ;Zi__EBQGEDUBES_:_NQBd8kt_()QBd86u_Edg8@gNGy_8NQ~
B8R19600lG86_G0b!IB96 -
()         PAGE  61 1 j
                                                                                                                                   }
ANSW'ER'          "7.19              _ (1.00) 7(Single pump ops in the loop that) provides the'best spray-is preferred to.obtain normal PZR spray' capability.                                             (1.0)
           -. REFERENCE
^7 LT&Q;CO-ROOO4,LElement #6; Catawba LP OP-CN-HO-EP1; Pgs 31-33; LPSO Objectives 5C and 7;_ Emergency Procedure
 ,            EP/1/A/5000/1A1, " Natural _ Circulation:Cooldown" KAIR 3.9/4.1 4.4/4.6-D           'OOOO17K101               010000K101                        ...(KA'S)
QUESTION           7.20              -(2.00)
In accordance with limits and precautions of                                            OP/1/A/6250/02
              " Auxiliary _Feodwater System":
a)    What TWO (2) actions must be performed if the CA pumps
                                                  ~
cavitate when' suction is aligned to'the hotwell?
b)I    What<TWO (2f automat'ic' actions may result.if operation of the CA pumps is attempted when supplied from the hotwell ~ when the hotwell is under a vacuum?
         'ANSWERJ            7.20               (2.00) a)     1)       -Trip ONE'(1) of the THREE (3) pumps AND;                                        (0.5)
: 2)        throttle flow as required.                                                      (0.5) 1)-       Will result in a pump trip OR;                                                  (0,5) b)
: 2)        switch over to RN and RC.                                                       (0.5)
REFERENCE
             'T&O CD-RO140, Element #4 (Step 2.24 of OP/1/A/6100/01);
Catawba LP OP-CN-HD-CA; Pgs 9-10, LPSD Objectives 7 and 9; Ops Procedure, OP/1/A/6250/02 " Auxiliary Feedwater System" l           'KAIR 3.7/3.9             3.8/4.1 061000 GOO 1            061000G015                        ...(KA'S)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
L b b __: _ ______________________._____ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ __       _    _   _

1 s
   .<b7(;_PBQgEQURES -' NORMAL _GENQRMOLt_EMEBQENQY_8ND                t                                         PAGE- 62        '!
'/                 ,
                       -8821069@lG86_GONIBOL LW                  .
                                                                                                                                   ]
j QUESTION: 7.21;                                              '(2.00)
              ' SCENARIO ~
The1 control: room 'has been evacuated and personnel are in the' process of shutting down'the unit-from the Aux Shutdown Panel.             The reactor was' tripped from outside the-control room land the reactor operator failed to
                           ' . verify rod bottom light                       f illumination prior.to evacuation..
Assumo'that the following plant' conditions' exists NC Tavg~* '495 degroes F PZR. Level = *25 percent (no load)
PZR Pressure ~ - *1595 PSIG Baron Concentration = '880'PPMB Boric. Acid / Tank Level = '90 percent
                                                       " Observed" 'BA' Flow'(with both pumps running and 1NV-238A/1NV-186A f ull y open) = '90 GPM
            ;'Using_.given Doron Control Data and Attachments 7-6'and 7-7
       , CALCULATE the MINIMUM amount'of-TIME.the boric acid pumps must be run in order to' ensure'that the NC system is borated to the MINIMUM level' called f or by AP/1/A/5500/17; Enclosure' NINEE(9).
                 --SHOW ALL APPLICABLE CALCULATIONS; NOTE ALL ASSUMPTIONS'-
l h
i l
I
     +
l
                       ?ff

                                             ,,, ,-- ~. ~ .                ,
               .CNS               ENCLOSURE 9:
        '.AP/1/A/5500/17          BORON CONCENTRATION ADJUSTMENT                            1 3etype e15 NOTE       IF Control Room Operator verifies that any rod NOT fully inserted, 150 ppm Boron should be added for each rod N_OT O     fully inserted.
NOTE       IF the Reactor was tripped from outside the Control Room or Rod Bottom Lights were NOT verified, the NC System should be borated to > 2000 ppm.
: 1. Determine Amount Of Boric Acid To Be Added:
o     Refer to OP/1/A/6700/01, UNIT ONE DATA BOOK.
: 2. Align Boric Acid Pumps To NV Pump (s) Suction Hdr:
o    Ensure following valves:
OPEN o     1NV-238A (Boric Acid To Boric Acid Blender Control)
AB-550, HH-)), 53-54 o     1NV-186A (Boric Acid Blender Outlet To VCT Outlet isolation)
AB-586, KK-50.
NOT_E      Amount of Boric Acid added should be calculated from pump run times AND observed boric acid flow rate.
: 3. Start Boric Acid Pump (s).
: 4. Add Desired Amount Of Boric Acid.
Page 1 of 2 a

                                             . u e v u v u s ur v , w u vy PAGE NO.
CNS                ENCLOSURE 9:
      . AP/1/A/5500/17          BORON CONCENTRATION ADJUSTMENT                            2 Retype #15
: 5. Secure Boration:                                                      ,
o     STOP Boric Acid Pump (s-).
o     CLOSE following valves:
INV-238A 1 NV-186A.
CAUTION         Due to the H2 pressure maintained in the VCT ( x30-40 PSIG),        l it is possible for the VCT head pressure to be greater than-FWST head pressure with a VCT level of 0%. To prevent loss of suction. supply to the charging pumps, the VCT outlet isolations (1NV-188A & 189B) should be closed when the FWST is the suction supply.
NOTE      IF Boric Acid Tank level is low, shutdown margin (and VCT level) can be maintained by supplying FW to the NV System through local operation of 1NV-252A O_R_ INV-2538 (NV Pumps Suct From FWST).
END i
l l
1 I
l Page 2 of 2 1

LL IZz__EBQQEDUBEg_;_NQBMBL2_Spyg8dGL _EMEBGEN9I_GND                                                                                              x                                                    PAGE 63 RADIOLOGICAL CONTROL l
YANSWER                 7.21                                                       (2.00)
LAccopding to " Note" in Enclosure NINE-(9); the NC System should be borated to (at least) 2000 PFM.
L                         Assuming that.the present NC baron concentration = 880 PPMB and desired NC boron concentration = 2000 PPMD - AND using Baron Control Data                                                              '12600 gallons is required, HOWEVER, because of present plant conditions, correction factor of 1.05 must be used, therefore, *13,230 gallons must be added.
13,230 gallons
                         -___.___________ = ~147 minutes of present pump oport cion 90 gallons / min
(*TWO (2) hours and 27 minutes of pump operation required)
Data. Determination worth 1.0 points Calculation worth 0.5 points
                                              ' Answer worth O.5 points E All owance f or answer based on between 13,000 and 13,500 gallons of boric acid being added - between 2 hours, 25 minutes and 2 hours, 30 minutes]
Errors to be carried forward
                        . REFERENCE T&Q CO-ROO81, Element #3; T&Q CD-SOO36, Elements #2 and 3;
                         , Catawba LP OP-CN-PS-NV; Pg 88; LPSG Objectivos 2 and 13.23;
                         ' Catawba Abnormal Procedure AP/1/A/5500/17 and Op Procedure
                         -OP/1/A/6100/04
                        -KAIR 2.4/2.9 3.3/3.9 000024A205                                      OOOO24K103                                                            ...(KA'S)
(***** END OF CATEGORY 07 *****)

LDz__99did1 SIB 8IIYE_EB99EQUBEgt_ggyp]IlgNS,_GNp_gid]I6110Ng                                                                             PAGE- 64 I <
2, . .         ..
I i
LOUESTION        8201                                                                . (1.00)
During a reactor. start up, at 3% of rated power it was noted that NI 36 Intermediate Range indication had not changed during'the~ start up.                                                                   ILC says it's a minor problem and will take'about!two hours lto correct.
       .Which' one of the f ollowing most accurately describes the allowances and limitations imposed by Technical Specifications.
NOTE: Applicable T.S.'s are provided, a)   Increase power to a maximum of 10% and hold there, b)   Hold power approximately where it i s, maintaining less than 5% until NI 36 is corrected.
c)   Continue the power increase to full load.
d)   Insert all rods and correct the problem with NI 36.
ANSWER          O.01                                                                    (1.00) a) (1.0 pt.)
        ' REFERENCE Technical Specification Table 3.3-1 k/a 2.0 /.3.4                                                              3.2'/ 3.6 000033G008-                                                   OOOO33K301                        ...(KA'S) l l                                                    (*****                                   CATEGORY 08 CONTINUED DN NEXT PAGE * * * * *)                 l 1
1

p 4                       8 I
OUESTION                   O.02         (1.00)
The plant is at 100% Power and "A" NI pump is tagged out of service due to mechanical problems.            Routine maintenance on the drain line between the KC inlet and outlet isolation to the "B" ND Heat Exchanger requires the KC to be isolated to the "B"ND Heat Exchanger.
Which one of the f ollowing most accurately describes the allowances and limitation imposed by Technical Specifications.
NOTE: Applicable T.S.s are provided, a)  Return the NI pump to operable status within 72 hours or be in at least Hot Stand By within the next 6 hours and in Hot Shut Down within the f ollowing 6 hours, b)  Return the NI pump and KC System to operable status within 72 hours, c)  Complete a Non Conformance report, notify the NRC and continue operation with increased surveillance per Technical Specification.
d)  Start a plant shut down within one hour.
ANSWER                  8.02         (1.00)                                       f d) (1.0 pt.)
REFERENCE T.S.        3.7.3 and 3.5.2 k/a 3.5 / 4.2          3.2 / 3.8 OO500 GOO 5           OO6000 GOO 5     ...(KA'S)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE    *****)

eiL_8DdlNIEIBGIIVE_EB9REDUBEEu_GQND1I19 Net _0ND_ Lid 1IBI1QUE                                      PAGE- 66
                .m
         .L                    ..
QOESTION                            8.03        (1.00)
A reactor st' art up is scheduled today Sept. the 26. Just-prior to going critical it was brought to your attention that the' monthly surveillance requirement'for the Baron Injection Flow Path had been missed in scheduling. The
               -completion dates..on the last surveillance tests were June 19,. Jul y 20, and August-20.
                . Which one of the following most accurately describes the allowances and limitations imposed by Technical Specifications.
June has 30 days,' July 31, Aug. 31, and Sept. 30 NOTE: Applicable T.S. are provided a )'      Hold present condition, do not make a mode change or power increase until the surveillance.is completed, b)        Continue the reactor Start up. Conditions are not outside the bounds of Technical Specifications.
c)        Complete a Tect Exception Report, explaining the circumstances and continue with the reactor start
                                                 .up.
d)        Go to Hot Standby and complete the Surveillance tect then continue with the Reactor start up.
            ~ ANSWER                              O.03         (1.00) b) (1.0 pt.)                                                                                                         j 1
l REFERENCE 1
T.S. 4.0.2 and 4.0.5 l-                 k/a 3.5'/ 4.2 006000G005                            ...(KA'S)
                                                                                                                                        )
f 1
(***** CATEGORY 00 CONTINUED ON NEXT PAGE ***4*)

lDz__8DdIUISIBBIIME_EB9CEgyBE$1_CgNp111gN$1_8Np_LidIIBIlgN@                                               .PAGE ~67
      -QUESTION                                8.04              !$. 00)
FILL IN THE BLANKS concerning Shift Manning and Overtime
       -Requirements per DMP.1-10 a)                           The Shif t Crew ' composition may be one less than the minimum requirements for'a period of time not to'oxceed
_____' hours provided immediate action'is taken to restore the Shift to full crew b)                          An individual should not.be permitted to work'more than
_____ hours in any 24 hours period nor more than ____
hours .in any. 48 hour period, nor more than ____-in any 7 day period, all excluding shift turnover time.
ANSWER                                  8.04-             (1.00) a)                           2.
b)                             16, 24,.72             (4 parts 9 0.25 pt.ea.)
REFERENCE Shift Manning and overtime Requirements OPM 1-10 k/a 2.5 / 3.4 194001A103                                    ...(KA'S)                                                            l QUESTION                                8.05              (1.50) a)                                The LEAST serious of the FOUR (4) Catawba Nuclear Station Emerg ency Pl an c l assi f i cat i on s i s ______________________.
b)                                A problem-'(event) which exists that can only effect the station; is being managed by station personnel AND CANNOT nor WOULD NOT further degrade any level of plant safety would be classified as _________________________________.
c)                              -A portion of the Fire Protection System has just been declared' INOPERABLE and the unit must be shutdown according.to the Technical Specifications.              NO fires exist AND this situation CANNOT nor WOULD NOT further degrade any level of plant safety.              This condition would be classified as _______________________________________.
--        ______._______m______-____.._m_               _ _ .

ar___end1NISIB011YE_ESQQEQUBK@i_GQNQlIlQN@g_8ND_LidlIGIlgNS                                             PAGE 68 1.' '-              .
          ,,)            Ls_.
ANSWER'               .B.05             (1.50) h             "a)                "a-Notification of an Unusual Event"              (0.5)
.c b ):      '"a Notification of an Unusual Event"                (0.5) c) .         "a Notification of, an Unusual Event"             (O.5)
: REFERENCE
,.            ~ T3<Q ' CO-SCO26, Element.#3 t< 4; Catawba LP OP-CN-HO-SEP; LPSD
              ,K/A 3.1 / 4.4
:194001A116
                  .                             ...(KA'S)-
o
           ' QUESTION .8.06                           (1.00)-
The. reactor i s at 45"/. power. A Boric Acid' Tan'k i s taken out of' service and all'other systems are in service.
What are the allowances or limitations.. imposed by the
              .. Technical Specifications?
NOTE:. Applicable T.S.~ are provided.
p.. -
ANSWER'                O.06             (t.00)
              'No action required (1.O pt.)
REFERENCE
              ' Technical Specification 3.1.2.2 k/a 3.3 / 3.8
:004000G005                       ...(KA'S)-
1
(*****' CATEGORY-08 CONTINUED ON NEXT PAGE *****)

69 fazuiGDdINISIS811Vg_ESQGEDUSES t_QgNQ11199@i_8ND_ Lid 1I611gNS-                                      PAGE
            ' QUESTION.'O.07~                         (1.00)
              ;During a-QA~ inspection it was discovered:that Steam Line Safety. Valves.SV21, SV22, SV15 and SV16 had all been set to relieve at 1205#. This'was discovered while at 100% power.
      - ' No one is presently on site that can reset the. safety
              . valves, and it will take approximately 6 hours for someone to arrive on site to reset the safety.
NOTE: Applicable T.S. are provided.
What: are the allowances and limitations,if -any, imposed by Technical Specifications,' assuming power operation.is to
: continue.
          > ANSWER'         8.07                      (1.00)
Reduce. Power 1 Range NI Flux' Trip Setpoint to 87% power.
(1.0 pt)
REFERENCE T.S. 3.7.1.1 and Table 3.7.'1,2,& 3 039000G011         ...(KA'S)
QUESTION       8.08-                    .(1.50)
Initial conditions: 100% power, B Charging Pump OOC for
                " Mechanical repairs", Surveillance test are due on A and B l             . Diesel Generators.
While perf orming the surveillance on "A" Diesel Generator it was noted that it took 10.5 seconds to reach 4160 Volts and 12.5 seconds to reach 57 Hz. The ti me i s . 0140.               At 0210 it has been decided to have the machine shop adjust the fuel racks.
What are the allowances and limitations imposed by Technical Specifications?                   (Include specific times as appropiate) l.
NOTE: Applicable T.S. are provided.
1.
l 1'
I

i J@t__0Dd1NISIBBIlyg_eggCgDUBEat_G9ND1119Nai_GND_ Lid 1IBIlgNS-                           PAGEn'70
     . .e
        'N            ' .:
            ' ANSWER                   8.08.
( 1. 50):
Take action within two (2) hours to place the' unit in Hot
               ' Standby.                  (1.5 pt)
REFERENCE LT,S..3.8.1.1 action C.1 T.S..3.1.2.4 T.S.-3.0.3 T.S. interpretation 3.8.1 and 3.0.3 k/a'3.4 / 3.9                                  3.6'/ 4.2 LOO 6000G011                           064000G011              ...(KA'S)
QUESTION                  9.09                        (1.00) 16:OO. Friday afternoon QA finds a deviation in the support for-P.he                A" Component Cooling Pump Suction Pipe (incorrect bol t, .si z e) . An OPERABILITY EVALUATION FORM is immediately l filed'with Design Engineering. Tuesday at 12:00, four (4) days later, Design Engineering declares the pump inoperable.
As'a: Shift Supervisor, WHAT ACTION WOULD YOU TAKE7 NOTE: Applicable T.S. are provided.
ANSWER,                    8.09                       (1.00)-
                '(The pump!is not' declared inoperable'per T.S. until the report is received from Design Engineering, then T.S. 3.7.3 l                becomes applicable.)
l-I            ' Restore to operable status by 12:00 Friday or be in at least
: j.               Hot Standby within the next 6 hours and in Cold Shutaown I                within.the following 30 hours.                                 (1.0) 1 REFERENCE-CATAWBA NUCLEAR STATION DIRECTIVE 3.1.14 sec. 5.3 page 5 k/a12.5 / 3.4                                     3.4 / 3.8 OOSOOOG011                              194001A103           ...(KA'S)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
_i__m_E____.1.m._____.__._.____m  _ _ _ _ _ _ . _

iu
             ;eL_iGQdlNISIB8IlyE_EBQCEDUBESx_CQNDlIlgug,_8ND_LidlIGIl06@                                                                                                              PAGE      '71 J '
QUESTION LG.10                                  (1.50) a)..At'10:CO-you enter a T.S. action statement that directs
                            'you,to be in-Hot Standby within 6 hours and Hot Shutdown within the following 6 hours.
Hot Standby is achieved in 3 hours.
                            ' At .WHAT TIME. would- you have to L e in Hot Shutdown?
g b). 'If.a shutdown or power reduction is required per 3.0.3,
                            ;WHAT is.the MINIMUM rate of power reduction por CNS.
t Directive 3.1.19 " Acti ons to take in case of Exceeding limits"7-c). .. I f a plant, cooldown is required per 3.0.3,                                                  WHAT is the MINIMUM. rate of cooldown to be used per CNS Directive l
3.1.19 "Act. ions.to take'in. case of Exceeding Limits".
1 ANSWER                                   8.10        (1.50)                                                                                                                           !
;                     a)'    22:00 ~(O.5^pt)                                                                                                                                                        i b)     10 %.per hour (0.5 pt) c). 10.deg.:per hour (0.5 pt)
REFERENCE                                                                                                                                                                     !
                                                                                                                                                                                                    \
Catawba 1 Nuclear Station Directive 3.1.19 Action to take in                                                                                                                  i case of " Exceeding Limits" k/a 2.5 / 3.4                                                                                                                                                                 l 194001A103                             ...(KA'S)                                                                                                                              l l
QUESTION                           8.11         (1.50) i Asian SRO during an Emergency condition, you're following the Emergency procedures.                                                                                                                                                      ,
What specific actions are taken - per OMP 1-4 "Use of
                     -Procedures"                         -
for...:                                                                                                                                 i a)     an' UNEXPECTED "IN JEOPARDY" (RED) is diagnoced.
b)     an EXPECTED "IN JEOPARDY" (RED) is diagnosed.

az__8DMlulSIB811YE_EBQCgDQBEQu_QQNDlIlgNQt_GNQ_61MIIGI1QNH                               PAGE 72-a-       -
ANSWER      8.11         '(1.50)
         'a)    Should immediately suspend the procedure in effect (0. 5 pt) and initiate the procedure to restore the Critical Safety Functions in jeopardy. (0.5 pt) b)   Ttus shif t supervisor has the option to initiate or 'not initiate the procedure to restore the CSF in jeopardy.
(0.5 pt)
(His decision should be based on an assessment of plant status, available manpower, and the likely effectiveness of mitigative actions in the procedure. )
REFERENCE OPM'l-4'Use of. Procedures page 7 k/a=2.5 / 3.4 194001A103        ...(KA'S)
QUESTION    8.12          (1.50)
          'PER OMP 1-5 " Independent Verification".
a)   WHEN may independent verification be waived, b)   Whose approval is needed for the waiver?
       ' ANSWER      8.12-         (1.50) a)   If the-individual performing an independent verification would receive more than a 100 mrom dose. (1.0 pt) b) ' Unit Coordinator _ or Duty Engineers approval.  (0.5 pt) i l
          -REFERENCE l
OMP 1-5 Independent Verification page 5 k/a 3.6 / 3.7 194001K101        ...(KA'S)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
l i
                                                                                                           )

Las__GDDINI5188112E_EB99EDUBES                        1   _ggNpillgNSx_@ND_LIMII8IlgNS                                                  PAGE 73     !
                               %                                                                                                                             )
8            .4.
1
         ^
QUESTION             8.13                 -(1.50)                                                                                                l LIfETSM, Work request:is generated.on the Feed water system.
             .a).         Hcn9 =are the Control room operators made aware of the TSM-Work request?
y-b4 LWhat is'done if the TSM' Work request affects a' system's existing-physical construction ?
c)- What is done if the TSM Work request affects the system operation?
           ' ANSWER              8.13                 -(1.50)
Will be . entered' in the Temporary Modifications logbook.
                  ~
a)
(0.5 pt) b)        _If-the. control room drawings are affected by the
                         ' Temporary Modification, the Supervisor will ensure that the affected drawing are marked to reference the
                         " associated TSM.              This will be accomplished be attaching-a small card to the affected drawing. The card should read "This drawing is affected by TSM Work Roquest (number). (0.5 pt) c)         If the Temporary Modification affects plant operation, the the Supervisor shall ensure that operations procedures are changed as necessary. (0.5 pt)
ANY' ACCEPTABLE WORDING
             ' REFERENCE OMP 2-14' Temporary Modifications k/a 3.7 / 4.1.
              .194001K102                        ...(KA'S)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
l-l                          ^ '

:92__0DdINISIBBI1YE_EBggEDUBESx_QQNp1119NS                   t _OND_LINIISIlgNS   PAGE~ 74
          'GUESTION           8.14        - ( 1. 00)
Concerning ADMINISTRATION AND CONTROL OF KEYS:
a)'     What are. WHITE TAB KEYS and when are they used?
1 b)' 'What are RED TAD KEYS and when'are they used?
I. .-
8.14         (1.00) s .-.. ' ANSWER a) , White' Tab Keys are working keys and are normally used.                             d i
(0.S) b)      ' Red Tab Keys are ' file keys. and are only used if the working key is'not in the key locker. (0.5 pt)
REFERENCE
:OMP.2-9.-page 4
             'k/a 2.5 / 3.4 194001A103'            ...(KA'S)
QUESTION           8.15         (2.25)
Per Station Directive 3.1.17 " Fuel Handling Interlocks".
LIST the three (3) conditions when the Fuel Handling
           ;eq'uipment interlocks may be bypassed.

iet__8Dd181EIBBILYE_EBQGEQQBEQu_QQNQlIlONQu_8NQ_61dlI8IlgNQ                          PAGE        75
   . ANSWER            8.15          (2.25) a)~        When specifically so directed by an approved written procedure, fuel handling equipment interlocks may be bypassed.       (0.75 pt) b )'     (If handling fuel assemblies, insert components or dummy fuel assemblies, fuel handling equipment interlocks may be bypassed.when the operator recei ves) verbal. approval from two (2)Loperations Group Supervisors, one oflwhom
              .must be the Shift-Supervisor or his designee, and the other being a. Supervisor in operations Group. (0.75 pt) c) , If fuel assemblies, insert components or dummy fuel assemblies _arelnot.boing handled, the Fuel Handling
,             Supervisor may give approval to bypass interlocks.
( 0. 75 -- p t )
REFERENCE CNS Directive 3.1.17 Fuel Handling Interlocks k/a 2.5 / 3.4               2.3 / 2.9
     -034000 GOO 1              194001A103   ...(KA*S)
QUESTION           B.16          (1.50)
You are Shift Supervisor, and a reactor start up is
     . scheduled on your shift. The reactor had been shut down due to a reactor trip.
a)      Who is responsible for completing a Post Trip review?
b)       If the person responsible for completing the Post Trip review recommends that the plant be restarted, how do they document their recommendation to restart the unit?

   - at__8DMINISIBGIIVE_EBQQSQQBESt_CQNQlllQN@u_8NQ_61MlIGIlgN@                                     .PAGE   76 ANSWER.                                  '8.16          (1.50) a)                         Reactor Engineer (0.5 pt) b)'                        By initialing and dating the appropriate step in (0.5 pt)' (OP/1(2)/A/6100/05), Unit Fast Recovery,    (1>rdI pt) Jg,(P/1(2)/A/6100/01) Controlling Procedure for Unit Startup. (0.26  j    pt)
                                                     , d2E REFEheNCE CNS Directive 3.1.18 page 3 k/a 2.5 / 3.4
        -194001A103                                  ...(KA'S)
QUESTION                                  8.17          (1.50)
State the administrative guidelines that allow procedural steps to~be performed out of sequence.
STATE ANY ASSUMPTIONS TAKEN TO SUPPORT YOUR ANSWER                            _
l i
ANSWER                                    8.17          (1.50)
The verbal approval of two Operators, (0.75) one of whom is a supervisor'who holds a SRO license. (0.75)
REFERENCE                                                                                                ,
1 OMP 1-4 Use of Procedures page 11 sec. B. 5 a                                                           .
ETOS CD SOOO1 Ele. 2 c&d k/a 2.5 / 3.4 194001A103                                ...(KA'S) i
                                                                                                               -l
(***** CATEGORY 08 CONTINUED ON NEXT PAGE ****t)   .
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _          _                                                         1

Uah_8pdINISIB8i1E_EBgCgggggs,._CgNp1I1gus,_egp_ lit!1IsligNS                                                                             PAGE 77-t
    .. i-.           .
i QUESTION - 8.'18                                               (1.00)
           'During..~the performance.of'PT/2/A/42OJ/11 " Emergency Boration Flow Rate verification", The accep'.ance criteria could not
           ?be determined due'to'a broken gaugn, ILC installed a
            ' temporary gauge'that could be used fer the test.
As?aeShift Superviser WHAT'would be your administrative actions?
  ' JANSWER-                                            8.18             (1.00)
                         ' Fill.outza " Procedure. Discrepancies Process Record" per (Station: Directive 4.2.1 Section.12) -(1.0 pt)
           . REFERENCE OMP 1-4.page 17
           .k/a 2.5 / 3.4 194001A103                                            ...(KA'S)
QUESTION' O.19'                                               ( .50)
As a Shift Supervisor, per-procedure OMP 1-4 "Use of Procedures", HOW~MANY permanent procedure changes would you Lauthorize bef ore requesting the OEDD f or a retype?
: ANSWER-                                       8.19             ( .50) 5 (0.5'pt)                                    O v-       Ab.m M *^m "* d V REFERENCE l           .OMP 1-4                                    Attachment 2 page 2      step I.2 k/a 2.5 /'3.4 194001A103                                            ...(KA'S) l l
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
L                 _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ - -

Os__02b1NISIB8IlyE_E8dgEpuBED1_CgypillONgt_8ND_LidlIBIlgND                                                              PAGE. 78
     . -i           . . .
8
* LOUESTIONl 8.20                                                                 (1.00) r3 iYour the Shif t Supervisor and the Electrical . Group is                                                                            l 1
replacing a damaged electrical cable that extends from a
          . motor operated valve in.the Aux Feed pump room, to its power
: source at 1EMXA.                                                                                                                  1 cThe electrical' group' informs you that the cable penetration                                                                       1 i
          .in the north wall of the. Aux Feed pump room has been damaged
           -and cannot tur secured. What action, if any, must you take                                                                       ..)
concerning this penetration?                                                                                                       4 ANSWER                               8.'20                                  -(1. 30) a)               Enter Tech-Spec. 3.7.11. Fire Barriers-(0.5 pt)
           'b):               Station =a Fire watch. (0.5 pt)
          ' REFERENCE CNG Directive 2.12.7 FIRE DETECTION AND PROTECTION k/a 2.5 / 3.4                                       2.7 / 3.5 086000G011-                                   194001A103                           ...(KA'S)
       -QUESTION ~ 8.21                                                                (1.00)
                                                                                ~
In accordance with CNS Directive 3.8.8 " Radiological Work Practices", what are the requirements if an Extra High Radiation Area can not be controlled by lock or guard?
ANSWER                               8.21                                    (1.00)
                            ~
Area shall be conspicuously posted (0.5) and a flashing 1ight shall be. activated 1to warn personnel to stay cicar of the' area (0.5).
REFERENCE l           CNS Directive 3.8.8, Radiological Work Practices p3 k/a 2.8 / 3.4 194001K103                                    ...(KA'S)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

Sz__6DdINigIBGIlyE_PBgGEggBES3_GQNDIIlgNS t_GND_ Lib 1IGIlgNS                  PAGE 79-QUESTION                    8.22        M r5fM                     .
g7 What Three (3) conditions must-b6" met in accordance with Technical Specifications, th'at allow the STA to assume the
           -control room command,f unction and serve as the SRO in the control room?                      f'.
(Include time li,31(ptions                    if applicable)                           1 ANSWER                      8.22        (1.50)                                          .
l ICD
* The shift supervisor is availa                    o the 1.
control room within 10 mip 's (0.5) o retf )
: 2.                  The assumption of SRO .4ics by the STA be limited to periods not in ex .os of 15 minutes duration (0.25) total time no to exc -d one hour uring any 8 hour shift ( or one hour 1   any 12 hour shift) (0.25)
: 3.                  The STA ha}s a Senioroperator license on the unit (0.5)
REFERENCE CNS Technical Specification 6.2.2 i k/a 2.5 / 3.4 194001A103                       ...(KA'S)
QUESTION                    8.23        (1.50)
In accordance with CNS Directive 3.1.1,                      " Safety and Delineation Tags" answer the following:
a)                     What two actions must take place before a " Human" Red Tag can leave the work station?
b)                     When can a Freeze Plug Operator transfer responsibility of maintaining the Freeze Plug to
                                  .another individual?
                                                                                                     \

Qi__0DdlNIGIB8IlVE_EBQCQQUBEQu_CQNDlllQNQu_8NQ_LIMlI611QNQ                                PAGE 80
   .      r
  ' ANSWER        B.23-        (1.50) a)    1. Work is complete (0.5)
: 2. All normal work request functions are satisfied (0.5) i                    d
: 1. Proper turnover has occuried and (0.5)
: 2. Maintenance personnel notified (0.5) )
b)    When he (the current freeze plug operator) notifies the Supervisor having operational responsibility. (0,5)
REFERENCE-CNS Directive 3.1.1, Safety and Delineation Tags, P'26, 27 k/a 3.7 / 4.1 194001K102         ...(KA'S)
   ' QUESTION. 8.24            ( 1. " . )  /, 4 While performing the surveillance test PT/1/A/4600/08B for-AXIAL FLUX DIFFERENCE per Technical Specification 4.2.1.1 the f ollowing data was recorded f rom the NIs.
     . NOTE: Assume Relaxed Axial Offset DATA FROM ENCLOSURE 13.2 IN VOLTS NI 41     NI 42    NI 43      NI44 A     .20291    .27762  .26559      .22591 B     .29241.   .28652   .27759     .25394 What actions, if any, should be taken?
Note: Applicable T.S. and work sheet are provided.
Show all work.
l i
j

Os__8DdlNIEIB011ME_EBQGEQUBES,._GQNQlIlgN$t_8NQ_LidlIGIlQNQ            PAGE 81
                                                     /, C)
;      ANSWER                      8.24       (1   )
r]o Perform action b of T.S. 3.2.
Ac%a         etc q vn     nc o (1.0 pt.)
: 1. . (Restore-indicated AFD to within target band limits within 15 min or)
: 2.           (Reduce thermal power to less than APL nd of rated thermal power and discontinue Base Load operation within 30 min.)
REFERENCE T.S.               3.2.1 and 4.2.1.2 k/a 3.7 / 3.9
       '015000A105                      ...(KA'S)

                         ^
                                                            ' TEST: CROSS REFERENCE              PAGE    1
  !QUESTION!                  VALUE-             REFERENCE
  .a:----             ~ ------                  .----------
     -05.01I                      1.00           RWCOOO2253
     '05.02-                    'i 00-          'RWCOOO2262 05.03-                    1.00           RWCOOO2263 05.04'                    1.50           RWCOOO2259' 05.051                   2.50'           RWCOOO2264 a.s 05.06                                     RWCOOO2265 2.00 05.07                     1.50        .RWCOOO2245
     '05.08:                     1.50            RWCOOO2250
     ~. 0 5 . 0 9 1               1.00'          RWCOOO2255 05.10-                    1.50           RWCOOO2258 05.11'                    1.50.          RWCOOO2261 05.12                    2.00            RWCOOO2247-
      '05.13                   .2.00             RWCOOO2254 05.14                    1.00            PWCOOO2249 e       05.15.          '
1.00           RWCOOO2260
     '05.16-                    ~ 1.00           RWCOOO2246 (05.17-                      1.50            RWCOOO2248
: 05.18-                    1.00            RWCOOO2252 05.19                     1.50            RWCOOO2256
     '05.20                      2.00'           RWCOOO2257:
105.21-                      1.00            RWCOOO2251 H30.00 5 06.01                      1.00           RWCOOO2268
     -06.02                       1.00            RWCOOO2270 06.03                     1.00            RWCOOO2274 06.04                     1.50            RWCOOO2271
     .06.05                          .50-         RWCOOO2266 06.06                        .50          RWCOOO2267 06.07                     1.50            RWCOOO2269 06.08.                    1.00            RWCOOO2272 06.09                     1.50-           RWCOOO2273 06.10                     1.50            RWCOOO2275 06.11                    2.00             RWCOOO2276 06.12-                   2.00-            RWCOOO2277 106.13                       1.75            RWCOOO2278
     --06.14                         . '7 5       RWCOOO2279 106.15-                     1.00            RWCOOO2280 106.16                      3.00             RWCOOO2281 06.17                     1.00            RWCOOO2282 06.18                     1.00            RWCOOO2283
      '06.19                      1.00            RWCOOO2284 06.20                    2.50             RWCOOO2285 H27.00 l    ''07.01                      1.00            RWCOOO2288                                               j i       07.02                   '1.00             RWCOOO2291
!       07.03                     1.00            RWCOOO2292 1                                                                                                           :
1 L
j i

TEST CROSS REFERENCE PAGE 2 L
QUESTION         :VALUE'             REFERENCE
   ?_2_s- J_        a_____.              __________
     "O7. 0 4' ~          1'.00          RWCOOO2295 107.05'             1''00         'RWCOOO2296 07.06-            1.00'          RWCOOO2297-107.07'             1.00           RWCOOO2298
     -07.08               1.00           RWCOOO2301 f    07.09~.          2.00            RWCOOO2306-
     .07.10             -1.50            RWCOOO2303 07.11             1'.25          RWCOOO2286 07.12           :1.50.           RWCOOO2287 07.13.           2.00-           RWCOOO2289.
E07.14            -2.00             RWCOOO2299.
      -07e15              1.00-          RWCOOO23OO 07.16             1.50.         'RWCOOO2305
      -07.17              1.00           RWCCOO2293 T 07.18:             2.00'           RWCOOO2294 107.19 1.00-          RWCOOO2302-
      -07.20'            2. 00 :.        RWCOOO2304 107.21             2.00            RWCOOO2290 28.75 08.01             1.00           RWCOOO2307
:08.02-           "_1. 00 .         RWCOOO2308 08.03    '
1 ~. 00.       RWCOOO2310 08.04-          :1.00            RWCOOO2317 08.05'.           1.50.          RWCOOO2330 08.06?'        -1.00             RWCOOO2309' E '08.07:                 1. ' 0 0 '     RWCOOO2311 08.08             1.50          ~RWCOOO2313 p: "C8.09                 1.00-          RWCOOO2314 08.10             1.50           RWCOOO2315
:08.11             ' 1. 50 .        RWCOOO2316 08.'12            1 .~ 50        RWCOOO2318
!       08.~ 13           1.50           RWCOOO2319 08.14             1.00           RWCOOO2320 L       08.15            2.25            RWCOOO2321-
,       08.16             1.50           RWCOOO2322 08.17             1.50           RWCOOO2323.
008.18-             1.00           RWCOOO2324 308.19                 .50          RWCOOO2325
     -08.,20              1.00           RWCOOO2326 108.21               1.00           RWCOOO2327 08.22           .1. 50 -         RWCOOO2328 08.23             1.50           RWCOOO2329
        .08.24            1.50           RWCOOO2312                              i B                     30.25                                                      l
                                                                                 \
116.00 DOCKET NO      413

    ,                       .                                                                                                               PT/1/A/4600/08B I                                                                                                    '
Retype   #2 Page 1 of 4 DUKE POWER COMPANY s
CATAL'BA NUCLEAR STATION                                                       ,
MANUAL CALCULATION OF QUADRANT TILT AND DELTA FLUX 1.0   PURPOSE
)                                                     1.1 To provide a means of manually calculating quadrant tilts (QPTR) and/or axial flux differences (delta flux).

==2.0 REFERENCES==

T-2.1     CNS Tech Spec 3/4.2.1, Axial Flux Difference 2.2    CNS Tech Spec 3/4.2.4, Quadrant Power Tilt Ratio                                                                                 i 2.3   OP/1/A/6700/01, Unit One Data Book 3.0 TIME REQUIRED 3.1    Quadrant Tilt - Two Performance Engineers for 30 minutes or one Operations NCO and two IAE Technicians for 20 minutes. Required
)'
frequency is at least once every 12 hours per Reference 2.2.
3.2    AFD - One Operations NCO for 10 minutes (if no DVM required). Two r
Performance Engineers for 30 minutes or one Operations NCO and two IAE Technicians for 20 minutes (if DVM is required). Required i
frequency is at least once every hour per Reference 2.1.
4.0    PREREQUISITE TESTS
;                                                    None f
5.0 TEST EQUIPMENT f
Digital Voltmeter - Fluke 8600A or equivalent (if required).
L                                             6.0   LIMITS AND PRECAUTIONS i
6.1    Exercise appropriate care when opening power range detector drawers and attaching voltmeter.
6.2    Prior to opening any ENB drawer, ensure S/G Level Program Select Switch and S/G Trip Level Setpoint Select Switch (both located on IMC2) are both set to some channel other than channel of drawer being opened.

PT/1/A/4600/08B Page 2 of 4 Retype   #2 7.0 REQUIRED UNIT STATUS Initial /Date
____/                             7.1     The test instrument has been signed out specifically to this  j test. Traceability is assured through the instrument history file. N/A this step if the DVM is not to be used.
8.0 PREREQUISITE SYSTEM CONDITIONS                                                                      i
                                                                                                                                    )
None                                                                                  )
9.0 TEST METHOD                                                                                         ]
9.1 Quadrant Tilt: Excore power range detector upper and lower currents are measured using a DVM attached to the panel meter test points.
The quadrant tilt is calculated using this data.
9.2 AFD: The AFD meters on Control Board 1 hcl are read and recorded.
If all channels are not more than 1% from the Tech Spec limits then excore detector currents are measured using a DVM attached to the panel meter test points. AFDs are calculated using this data.
10.0 DATA REQUIRED 10.1 Excore power range detector upper and lower current readings (if ne ces sa ry) .
10.2 Control Board AFD meter readings (for AFD only).
10.3 Full power calibration currents and M factors (for AFD only) for the power range upper and lower detectors.
11.0 ACCEPTANCE CRITERIA 11.1 QPTR is calculated and recorded on Ecciosure 13.3.
11.2 AFD is obtained and recorded on Enclosure 13.4.
12.0 PROCEDURE NOTE:                   Each section of this procedure may be performed independently.
The unused section should be N/A'ed.
Initial /Date 12.1 Calculation of Quadrant Tilt.
__ j,___ 12.1.1                                 Verify that Section 7.0 is complete.
()u edron B1

PT/1/A/4600/08B Page 3 of 4 Retype   #2
                     /      .12.1.2           Direct IAE or Performance to complete Enclosure.13.2 to obtain upper-and lower power range excore detector currents.
NOTE:             10105 SWR may be used to direct IAE to perform this step.
                    /        12.1.3           Complete the calculations on Enclosure 13.3.
                    /        12.1.4           Verify that Acceptance Criterion 11.1 is set.
                   /         12.1.5           Notify the appropriate Unit SRO or NCO of the results of this test.      See Reference 2.2.
                   /         12.1.6           N/A any unused procedure steps or enclosures.
12.2 Calculation of AFD
                   /        12.2.1            Record' time, power level, and AFD meter readings (located on IMC1) on Enclosure 13.4.
                   /        12.2.2            Compare AFD readings obtained in Step 12.2.1 with the AFD limits shown on Figures 1.1 in OP/1/A/6700/01, Unit One Data Book.
                   /,       12.2.3            If ' all four channels indicate an AFD more than 1%
conservative relative to the limf.ts shown in the Unit One Data Book then go to Step 12.2.7. - Otherwise, N/A this step and go to Step 12.2.4.
                  /         12.2.4          . Verify'that Section 7.0 is complete.
                  /         12.2.5           Direct I AE or Performance to complete Enclosure 13.2 to obtain upper and lower power range excore detector currents.
NOTE:             10105 SWR may be used to direct IAE to perform this step.
                  /         12.2.6           Complete calculations on Enclosure 13.4.
                  /-        12.2.7           Verify that Acceptance Criterion 11.2 is met.
                  /         12.2.8           Notify the appropriate Unit SRO or NCO of the results of this test.      See Reference 2.2.
                  /         12.2.9           Repeat Steps 12.2.1 through 12.2.8 as necessary using Enclosure 13.1 to record additional signoffs.
                  /         12.2.10          N/A any unused procedure steps or enclosuras.
1 1
g4,slio. B 'N

=-~          -- -                     -   -                     _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l i
I PT/1/A/4600/08B Page 4 of 4 Retype g 13.0 ENCLOSURES                          ,
13.1 Multiple Signoff Sheet 13.2 Reading Power Range Drawer Currents 13.3 Quadrant Tilt Calculations 13.4 AFD Calculations
                                                            ?-
1 1
I l
Qank B t4

                                                               ^
PT/1/A/4600/088 Pega 1 of 2 Retype   #2 ENCLOSURE 13.4 AFD CALC 1.ATIONS Contro1' Board AFD Meter Readings:
N-41.a            _%      N-41 =              %        N-43 =      %      N-44 =       %
Fower Level =            %          Time =
l Initial /Date
                                                                           - g,.
           /         13.4.1     Transcribe voltage readings recorded on Enclosure 13.2 into Column A of table below.
           /         13.4.2     Multiply each voltage in Column A by 1000 to obtain current in pA.
Record results in Column B.
           /-        13.4.3     Record the calibration current for each detector. channel (in pA) in Column C.         These currents are 34sted in Table 2.2 of the Unit One Data Book (OP/1/A/6700/01).
           /         13.4.4     Divide each channel's measured current listed in Column B by its corresponding calibration current in Column C.           Record results (relative flux) in Column D.
           /         13.4.5     Record the M factor for each detector in Column E. These factors are listed in Table 2.2 of the Unit One Data Book (OP/1/A/5600/01).
l        A           l         B        l     C     l      D        l             E   l Channel l Meter Reading IMeas. Current l Cal. Current ' Relative       Fluxl M Factor 1 l N-41A     l                    l                  l             ,             I                 l I
i           I                    I                  I           I               I I N-418     l                    l                  l           l'              l                  I I           I                    i                  1           I               I                -l l N-42A     i                    1                  1            I               I                 I I           I                    I                  I            i               1                 I l N-42B     l                    l                   l           l                l                 l I                I                 I l           l                    l                   1 l
I N-43A     I                     l                  l            l               l I            I                    I                  I            i            -l                   I l N-43B      l                    l                  l            l                1 I            I                I                 i 1           I                     I                                                                  '
l N-4LA     l                     l                  l            l                 I
                                                                                                              ~
: y. ;,7 -           - ~ - - - -l                    l             l                l 1          _l                     l                   l             l          __I_________
            /         13.4.6     Complete the next page to calculate AfD.
Qu thion           h.b

PT/1/A/4600/08B Page 2 of 2 RetYP8   #
    ,   .-                                                     F3 CLOS M 13*
AFDCALClk.ATIO!:S AFD Calculations:
Half the difference between each pair of upper and lower detectors is multiplied by the correction factor M.
l                              NOTE:     Indicate appropriate sign in final results. Use N/A if detector
(.                                       is inoperable.
                         % 4 Flux (N-41) =    [RF(N-41A) - RF(N-41B)] x M43 x 50%
                                          =   [
                                                                      )x          -b0%=              % a Flux (AFD)
                         % 6 Flux (N-42) =    [RF(N-42A) - RF(N-42B)} x M 42 x 50%
                                          =   [
                                                                      )x            x 50% =          % a Flux (AFD)
                         % 6 Flux (N-43)'=    [RF(N-43A) - RF(N-43B)) x M43 x 50%
                                          =   [
                                                                      )x            x 50% =          % a Flux (AFD)
                         % 6 Flux (N-44) =    [RF(N-44A) - RF(N-44B)) x M g x 50%
1
                                          =   [
                                                                       )x            x 50% =         % a Flux (AFD)
Enclosure Completed By                              -
Date Calculations Veri' ted By                              Date 9

   ~** . hhn $//[
e f.sf 2
* SOURCE _ .PT/1/A/4600/05F PREPARED BY .M.W. Hwes
                                                                                                  ~
EFFECTIVE DATE _1/4/88 OP/1/A/6700/01 UNIT ONE DATA BOOK TABLE 2.2 EXCORE DETECTOR DATA FULL POWER CURRENTS DETECTOR    UPPER (microAMP)       LOWER (microAMP)    M FACTOR N-41 297.8                   30f.8             1.491 N-42         286.2                   301.6             1.468 N-43 273.8                   292.2             1.471 N-44         237.8 267.3             1.418 NOTE: THIS FORM IS TO BE USED TO RECORD THE MOST CURRENT TEST DATA Q,cMo* 6#
L________  --  - - . _ - --

Graph for N- 41                                                                                                                                              OP/1/A/6700/01                                                                      Source     PT/1/A/4150/08 UNIT ONE DATA BOOK from                            33                                        EfPD                                                                                                                                                                   Prepared By      M.;;. Ha.as FIGURE 1.1 to'*                            64                                        EFPD                                                                  TARGET FLUX DIFFERENCE ARO AND EQUILIBRIUM XENON
                                                                                                                                                                                  -0.51 100                                                                                          ;
                                                                                                                                               ~                                ~
;                                                                                                         j-20,100)f                                                                                                     (10,100)
I                                                                                                         f                 I                                                                                       1             ,                                            ~
Z UNACCEPTABLE 7 /                                                                                                                                                                         !                     UMCCEPTABLE r OPERATION .h[=                                                                                                                                                                ,                                  OPERATION l                      *   ~
                                                                                                                                                                                                            -,- A 1                                                                                                   3                                                            ,
I                                                                                                     g i
i I                                                                     i 1
I-                                                                     i                              a 1 2
80                                                                      ,
                                                                                                                  /                                                                       ',                                   i,:
1 s1                    .
                                                                                                                                                                                          ;                                   _1
                                                                                                      - .- j                   - - .                   .
q               1
                                                                                                             -j                 ,
1
                                                                                                                        --~                                                                                                         '
                                                                                                             ,f                                                                                                                   'i
                                                                                                          -                                                                                                                           1 I
                                                                                                                                                                                                                                         \>
,                                                                                                    I                                                                                                                                     y l                                                                                                 I                                                                                                                                         g
                                                                                              #                                                                                                                                             1      I i                                                                                                11 i                            i-
               , 60                                                               /                       ,
                                                                                                          '                                                                                                                                   i_
w                                                            !                                                                                                                                                                   '-
3
: a.                                                -/,
                                                                '                                         '                                                                                                                                                                   ~~~
              ~
3                                          j                                                                                  - ACCEPTABLE OPERATION:                                                    .                             !
i g
1
             -                          (-36,50)                                                                                                                                                                                                         (21,50)                    -
z                        -. ,
u E
et e. w.e i
I I                                  i y
20                                                                                            .
i                                                                                                                  .
1                                                                                                                  I 4                                                                                         i A
_                                                                                      i j    -
4                             ;              .                                                ___ _             _
                                                                                                                                                                                                                                                                               .H
                                                                                                        -l 1
j                                  i        i              .__j
_.3 -                               "                           j                                                                                      L ._ -_ -       ^ L .._l Z : "_
                                                                                                                                                         .   . . ' __T_~)         ___
                                                                                                      -4
                                                                                                                              -f-.--.~_4--_-(..                                                                   *
                                                                                                                                                                                                                                 -+                4+-*              j---*+         ~ ~ *
                                     -40                                                            -30                      -20                       -10                                   0                 10                                 20               30                   C FLUX O!:rE:ENCE, t.! (*)
Qwes4 ion 9.d

__                     _.             ._           _ = _ .
Graph for N                   42                                                                     OP/1/A/6700/01                                                         Source               PT/1/A/4150/08 UNIT ONE DATA BOOK from           33               EFPp                                                                        FIGURE 1.1 Prepared By :.1, u . d he s _ .
l                                    EFPD                                                     TARGET FLUX DIFFERENCE l
* t o ** 64 ARO AND EQUILIBRIUM XENON
                                                                                                                       -0.39 inn
               ~-                                                             . ,                   .-            -                            s                                       . . , . . _ . . _    .
                                              - (-20,1001,... -.,                                                        --
                                                                                                                                           ....I.
                                                +_                           ,f                                                                4(10,100)                                                                    ---
:Z UNACCEPTABLE W '-                                                                                                           !'
UNACCEPTABLE
:r OPERATION L/                                                                                                                  ;                                OPERATION E                                                 i                         1                       i I                        i i
i                                                                        I                                                                             1                      I                          I l                                                                       j                                  - _ .                                        1                     ,
I          i                  i                                                     's                  i                                                   i
                                                                   /                 -             4-                       a 9
3.g _
i 80                                              i-                                                                                            i
                     -                                     j                                .- ..:                      Q
                                                     -,                       +-             _.
                                                                                                                  - .e                                      _ \,               .                                                    ,
I                                                                                                    \               !
I__.-                                                                                                  1 I                                                                     _                                _1 l
I                                             1                        g                                _1 I                                                                        !                                   1 E                                                                                                             1
                     ~
J                                                   k                         ,                                    1 J                                                    I                        I                                      1 E                                                      i                                                               1 T
I                                                                                                                        t
: 1.                                     ,                                             ,                                       n
                                         '                                                       ~                             ;                                         '
i
                                        /--4I                                                                                 4
                             ~1                                                                                             i                                              k,
       ,       60                     1                                                                                                          .
w                             /                                                                                                           !                          i 8
a.
                                .I 1                                                                                                                                                t                                         --1 2,,                     j                                                           ACCEPTABLE OPERATION:                                                                 .;                                                  ;
       #                                                                                              1 E                                                                                              1 (21,50)                                   ~'
       =             -
(-36.50)                                                                       i w                                                                                              1 v
x w
Ch.
40 Y
l                                                                                                                              !
A i
20                                                                  .
i 3              . . . _ _ . . . _                                                                                                                 4 s _ -. ...___.
                                                                                                                                                                                                                      . -_4
                                                                                                . _ . _ . _ _ _ _ _                                                               i                    y 3
i,
                                                                                                                                                                                                           -3 . _ _ _ . - _ .
                                .                     _ _ _ _                                   _ _ . _ _ . . . . _ _ .                                                            i.                                    -
                                                                            -___4______...__...___-___,                                                                                                       _ . - - _ _ . _ _ -
                      . _ _ -_-                                                          __.___.._....___3___                                        _ _ _ _ .                                           -4_- -- -.--
0
                   -40                        -30                              -20                 -10                            0              10                              20                        30                      ::
                                                                                                        ..r       ::::E Es:E, f.! (t)
S weslien 8M

pp cov v 7
Graph for N-              43 OP/1/A/6700/01                                   Source PT/1/A/4150/06                                         i 33                                                      UNIT         E DATA BOOK l    from                      EFPD gp                                        Prepar d By li.W. H6wes l
to-*    64                CFPD TARGET FLUX DIFFERENCE l                                                                  ARO AND EQUILIBRIUM XENON
                                                                                    -0.65 100                                             1             i
                                       ,-20,100l[
(                                                          ,{ (10,100) :-
1_               I                                         .g                                                                               -
Z UttACCEPTABLEZI                                                                                             UNACCEPTABLE OPERATION Q_                 ,
I,                           OPERATION I                   -                              ,                             i
                                                  ~l .-                 I                                \,                           i 1
                                          ->                                                              1.
80
                                            .1 f-
_:A!  .r 4
_ j.--
g_
                                          .l.                                                                  .
i                i                                                   1\                      l I                T~
                                       .1                                                                          n, f
1
                                                                                                              -i                      ;
i                 i                                                     >
                                   ,f!                                                                                g I                                                                                     ',
r m   60                   /                                                                  .
w                       I                                                                                           i 8
m                  ~/                               '
i
                                                                                                                                                                                     ~
3
       -                 E I                                    ACCEPTABLE OPERATI0ft                                         !,
1
       -            (-36,50)                                                                                                      (21,50)                                              ~
5u         ~
QC      ,
i 40 1
_ _ __7 20                                                             .
I 1.
                                                             !~           f
:        a                                                                   .
                            ,                                       __t--                                                                 '
___n._j
__.-           i      __ _t _ -                                  . -
3 _ :{r_d
                                  -+
                                                           = -- xd _- --                        2           ._.               '.                           xx::::d 0-
                                                                .___4       '
__..                                    _tz ___ _ ir:- " n
              -40                  -30                   -20          -10                0        10                         20                         30                               O FLUr DIFFERENCE, al (1) bsu                      Di

pp se/ S' Graph for N-                  4a _                                                            OP/1/A/6700/01                                                    Source          PT/1/A/4150/08 UNIT ONE DATA BOOK frca             33          EfPD                                                                                                                              Prepared By d. W. Howes l             .
FIGURE 1.1 l
to "         64              EfPD                                                TARGET FLUX DIFFERENCE ARO AND EQUIL18RIUM XENCN
                                                                                                                                      -0.52 100                                                    >                          - - ~ ~                                                              --.                        . _.-
3 -20,100,JJ                                                                               g (10,100) __                                                       __
i                     1                                                                     i r UNACCEPTABLE,                          ,I                                                                       i,                           UNACCEPTABLE r OPERATION                      i /
1                            OPERATION             __.
I                              i                                              1                                                               -
l
                                                                               ~[                                                                                                                                                              '
1                                                                                     1" I                                                                                       1                                      i f                 .                                                               -ai :                                         l                                 1 4_I                                                                                                                   ._
80                                                                                                                             'i                                       ~                            ~
1 rl-                     l-                                      _
: p.                        -4;                 l E                                                                i y
I l         -
                                                                                                                                                                           \ I I                                                                                                      1 F                        i                                                                               g J'                          l                                                                                1 J                              '
l_
E                                                                             i                                   1                                                  ~
I                                                                              I                                    1 E                                                                               I                                     1 1                                                        '
1 I                                                                                 :                                      L ,
E                                                         '                       I                                       1 1 60                 /                                                                                                                          ',~
I                                                                                                                            1 LJ                    E                                                                                    i                                       1 3                     l                                                                         ---
                                                                                                                                             !                                          j'
_d I                                                                                                                                                                               ~'
8                   I                                                 ACCEPTABLE OPERAT10ft                                                              S
                                  ;                  /                                                                                                                                     i a                                                                                                                                                                                                               e w             (
__-36,50)                                                                                                                                        (21,50)                                    M i
                                  =
w U
E                                                                     I w
40 i
1 4
l
                                                                                                                                                                                                               $                                   3, 1
a i                                                                                          k i                                                                                                                            -
20                                                                                                                                                                      ,                                   ;
1                                    I
                                                                                                                                                                                            ',                  ~
i-                                                                                                                    H e                                                                                                      .
1
                                                                                                               . L-                                             ,
T--                                        i                           ;-      1 1                            '                   ,
                                                                                                                                                                                                                         --- , _ _ . a,
                                                                                                               --. _ 4
_y -.- ~~~4.__..-.-                                 . , . . -     .4- ~~ - -*-                                      + - ~ * * * - - -
* 4      -
j__             .
                                                                                                                                                               +_                          __                  . - - -
                                                                                                 +      _ _._ _..__.                                      _    +____.__.___.                                                    . - - -
                                                                                                                   ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~                ~     *~~~~~~~~~                           ~ ~ ~ ~ ~ ' ' ~ ~ '                       ~~
0
                                             -40                      30                    -20                   -10                           0              10                          20                  30                                0 FLLX C;rFE*ESCE, t! (%)
- _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ ._.                                                                      (ksn                                 b}}