ML20216C074

Forwards Comments on NRC Exams Administered on 870603.Tech Spec 2.10.2 Indicates That Answer Key Should Be Revised to Read as Stated

ML20216C074
Person / Time
Site:	Fort Calhoun
Issue date:	06/06/1987
From:	Andrews R OMAHA PUBLIC POWER DISTRICT
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20216B978	List: ML20216B973 ML20216C049 ML20216C074
References
LIC-87-403, NUDOCS 8706300211
Download: ML20216C074 (15)

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f Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 y_ Q ]{g ] %l 3 402/536 4000 's June 6, 1987 g,, 9 gg7 LIC-87-403 U LO Mr. Robert D. Martin Regional Administrator Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011

Reference:

Docket No. 50-285 Review of the NRC examinations administered June 3, 1987

Dear Mr. Martin:

Personnel at Omaha Public Power District have reviewed the NRC examina-tions which were administered on June 3, 1987. Our comments on these examinations are attached. 'i &p ul R. L. Andrews Division Man 4ger Nuclear Production Division RLA:Ikw Attachment c: Ralph A. Cooley c: w/o W. A. Paulson, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector B706300211 nyos22 PDR ADDCK 05000285 PDR Employmen in Ecual opportunity 45 W4

g+ d i ;;. _ - I e q f Ouestion5.U2/1.03 (2.00) Whatarethree(3) reasons lfortheCEAInsertionlimit? l - ANSWER. I 1. Maintain acceptable power distribution limits. (0.667) l -1 4 2. Maintain minimum shutdown margin. (0.667) l:t ( 3.- - CEA' misalignment effects limited to-acceptable levels.- (0.667)- -{ QMFE:' Further review of'_ Technical Specification 2.10.2 indicates that the answer key should be revised to read as follows: 4 IL. Maintain acceptable power distribution limits (acceptable power

peaking. factors) 2.

Maintain minimum shutdown margir.. 3.- CEA'm'isalignment. effects'are 1imited to acceptable levels. ~ 4. The. potential consequences of a CEA ejection accident are limited to acceptable levels. Any.three at 0.667 each,

Reference:

Bases for Technical Specification 2.10.2. .The OPPD examination bank will be updated to reflect this information. f I f

.t 4 Ouestion 5.03/1'.05 ~(1.00) - How and why does increasing boron concentration affect-AXIAL power distribution? ' Assume the reactor is operating at 50% power. 1 -ANSWER: Increasingboronconcentrationmovespowerupthecore(0.5)becausethe differential temperature across the core' increases and the colder, more Boron dense water at the' bottom'of the core makes the boron worth more. makes ASI more negative. (CONCEPT-0.5) REFERENCE FCS Rx Theory 'QCh : 007-005-01-C-03-3.05-0001 COMNT: 'At the Fort Calhoun-Station the turbine is'normally operated on." load-This'means that the turbine control valves do'not change position limit." in response to' varying steam conditions. Since the turbine' throttle valves would not reposition in response to a change in boron concentra-

tion,theheattransferrate(q)wouldnotchange.

q = m Cp delta T in ~ There-the primary system. q, m, and Cp would not change significantly. -fore, the' differential temperature across the core would not increase. The answer key should be revised by eliminating the phrase "the differ-ential temperature across the core increases and..." l o i

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b 0uestion 5.07/1.12 .(1.00) .i , Describe the two (2) fundamental.operatingconditions(whichmaybe a encounteredduringnormalpoweroperations)when.thedifferential j temperature across the core is not equal.to the. differential temperature l across the steam generators. K ] ANSWER: ,1 1._ During power changes i 2. When SG steaming unequal. (2 answers 0 0.5 ea.) I COMENT: ' j 1 .It is not clear from the wordingLof the question that power increase and i power: decrease would not be considered to be'diffe'ent fundamental r 1 operating. conditions. Therefore, the answer key should be. revised to read as follows:- 1. During a power increase (plant heatup/Tave: increase)

2. 'During a power. decrease'(plant cooldown/Tave decrease) z

~ 3. Unequal steaming of the steam' generators. Any 2 at 0.5 each.

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t,, Question 6.03/2.03 (1.50) I ' Whyis..ComponentCoolingWatersystem(CCW)flowlowerduringpost-DBA conditions than during normal operation? ANSWER: During post-DBA' conditions, fewer loads are supplied (0.75)- system flow. resistance.is' higher (0.75),andflowis.consequentlylower.. (non-essential.loadsare. isolated) COMMENT: Question 6.03/2.03 should be deleted from.the examination. The question As can'be-statement is incorrect.and could have confused the examinees. seen in'the attached pages from_ lesson plan 7-11-6,. flow from each component cooling water pump-is lower during post - DBA conditions, but total component cooling water system flow is higher during past DBA -conditions. il t S

x e,; 5 - f,' -t . - 1 l0uestion'6.04. . (1.00). \\ Howmuchpressurizersprayflow(eithergpm'or%)is. required;tocounter-balance all-900 kw of heaters? . ANSWER: (Either of 2' answers; +/- 10%; 1.0) 53 gpm.or.17% CO M NT:

At least-partial credit should be awarded to an examinee if he calculated the required flow rate based on the change in enthalpy of the fluid.

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. l: 1 o -Question 6.07/3.06 (1.50) Match the appropriate.RPS trip to the reasons for bypass below. ] MATCHING. Each trip may'be used more'than once or not at all. ) Allows for low power physics testing.

1. High rate of.

a. power change. b. Bypassed when NI's less than 15% because of NI inadequacies.

2. Low RCS flow.

~ Allows clutch'energization when

3. Low SG press.

c. . plant is in cold shutdown.

4. TM/LP d.

Bypassed when NI's < 1EE-04% to eliminate spurious trips. '5. Loss of Load, Adequate' protection provided when e.

6. APD power < 15%.

ANSWER: a. 4 or 2 b. 6 c.. 3 d. 1 (5 answers 00.3ea.;1.5) e. 5 COMENT: Pages 104 and 105 of Lesson Plan No. 7-12-25 state two bases for allowing bypass of the APD trips: (1) because of NI inaccuracies at extremely low power levels; and, (2) even if 15% power was generated in one half of the l-core, no limits would be threatened. Therefore, either 5. or 6. should be The OPPD exam bank key will be accepted for full credit as a match for e. revised accordingly. L t t

I l Question 6.08a/2.08a (1.00) Whatarethree(3)ofthefourconditionsnecessaryfora" fast" transfer of the 4,160 volt buses? l ANSWER: l a. 1. Lack of source synchronism. 2. Uncleared fault (s) exist on the bus being transferred, 3. The alternate source is NOT at the proper voltage. 4. The original supply breakers have NOT opened. (Any 3/4 @ 0.5 ea.) COMENT: The answer key should be revised to read as follows: 1. Sources are in synchronism. 2. No uncleared fault (s) exist on the bus being transferred. 3. The alternate source is at the proper voltage. 4. The original supply breakers have opened. 5. The AUT0/0FF AUTO switch ("43") is in AUT0. J Any three of these five at 0.5 each. l

Reference:

Pages 36 and 37 from Lesson Plan 7-13-2 and electrical diagram from the student handbook for this lesson plan. ] i g

T ? e c.- ; Ouestion 6.09a/3.09a (1.50) 'What-three'(3).conditionsLinitiatetheFeedwaterRegulatingsystem ' protective ramp function? ANSWER _: .a.

1..

Turbine trip Feedwater regulating system'in automatic: 2._ 3.. Feedwater regulating. valve >'5% open- ~(3-answers 00.5ea.;1.5) COMENT: The answer key should be revised to read as follows: 1. Turbine trip 2. Feedwater regulating system is in automatic 3 3. 'Feedwater regu'lating-valves >5% open - 4.' 'AUT0/ INHIBIT switch is in AUTO Any.three at 0.5 each.- Block diagram from the student handbook for Lesson Plan

Reference:

7-12-31.. "What .It.is recommended that this question be reworded to clarify it. .three (3) conditions, permissives, or system lineups must be met for initiation of the Feedwater Regulating system protective rampdown function?" l I t T

(,, 'A- --Question 6.09b/3.09bl (0.5) Once initiated, how can the ramp'be stopped, other than by use of the ramp' -stop button on-the man / auto station? .w. ANSWER: Reset the turbine: trip. P COMENT: ~The answer key should be revised to read as follows: 1. . Reset the turbine trip .2. AUT0/ INHIBIT switch in INHIBIT Either response acceptable for full credit.

Reference:

Page 37 of Lesson Plan 7-12-15. -g 9 [ t

f'_, i c a, Ouestion'6.10/3.11 /(1.00) j Other than the Reactor. Regulating system, what two_(2) uses are made of .the N11 power range control channels?, ANSWER: 1. Input to p'ower ratio calculator. .j l 2.- Display: axial shape index. l' f(2 answers 0.0.5ea.;1.0) 1 i I CONLEMI: c _The answer key.should be revised'to read as follows: L .' Input to power ratio calculator / recorder 1 ~. 2. Provide' indications of a subchannel deviation Provide input to.the computer (for calculation of. tilt and rod 3. overlapping / sequencing) =4. Provide. indication of power lleyel Any two at 0.5 each.. Pages 64 and 65 of Lesson Plan No. 7-12-19 and Figure 1.7.

Reference:

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t ,,i P l<! ' !Ouestion 7.'01/4.02f - (2.00) 'What are three'(3) of the five types of information which are provided by-a' Radiation Work PermitL(RPP)? ANSWER: 1. Clothing.& pr.stective equipment required. '2. ' Allowed. individual exposures (without additional authorization) 3. Job to..be performed. '4. Description of'the hazards involved. 5. Monitoring. requirements.

C0091ENT: -

The answer is based on the general statement on page VII-2-9 of the Radiation Protection Manual. As. indicated in this statement,.all requirementscanbefoundinRPP-20,RadiationWork-Permits (RWP). Therefore,' the answer key should be revised to read as follows:

1. ' Clothing and protective equipment required 2.

Allowed individual exposures (without additional authorization) 3. Job to be performed l l 4. Description of the hazards involved

5.. Monitoring requirements 6.

Dosimetry requirements 7. Radiological conditions

8. Special instructions.

Any three. answers at.667 each.

Fr. 'R y a r.- a a..,, Ouestion 8.01/4.13-(2.00). ( j MATCHING. Match each of-the colors and-descriptions with the correct tag type below.. 0ne color and one description should be used for each tag .'Indiv.idualcolorsand'descriptionsmaybeusedmorethanonceor-

e. -

l' type. not at'all.- (TYPICALANSWER: e.o,9) TAG TYPE C(; LOR- .a. DANGER, 00 NOT OPERATE 1, white / red b. CAUTION 2.. red / white c. TEMPORARY CHANGE 3. orange d. HOLD ORDER 4. yellow DESCRIPTION .5. Used by System Operations for electrical system switching.'

6.

Special instruction in component operation. 17. 0peration will. damage equipment or pose personnel hazard. 8. Equipment will be operated in a test position or mode. ANSWER: a. 2, 7 b. 4, 6' c. 3, 8 d. 1, 5 -(8 answers 00.25ea.;2.0) COMMENT: There is no difference between " white / red" and " red / white." Therefore, the answer key should be revised to read as follows: a. 2.(or 1), 7 b. 4, 6 c. 3, 8 .d. 1 (ore 2), 5 G:.

g,m, v s-4.. ' Ouest' ion ' 8.06 (1.50) Whatthree.-(3) requirements ~mustbesatisfiedtomakeatemporary E(On-the-spot)1 change to a procedure? ANSWER:: 1 1. Intentunaltered(not'anUSQD). Approved.by two (2) members of plant supervisory staff,Lat leastL1 an 2. l ' SRO.' 3. The. change is documented, reviewed by the PRC, and approved by.the Manager-FCS~within 14 days of implementation. l(3. answers 00.5ea.;1.5) -COM4ENT:

1t should be noted.that the PRC (Plant Review Committee)'is the'onsite l

Lsafetyl review group which is comprised of members of the plant supervisory -staff. Therefore, PRC should be acceptable in lieu of plant' supervisory staff. 'l 1 a

m. c.3 ~. / : e -. v :..... Question 8.10-(1.50) a. Which keys'may be removed from the Operations Key: Depository without completion of the Key Log sheet? _(0,5). ~ b. Which keys:may be removed from the Operations Key Depository'by other Lthan the Shift Supervisor? When and by whom? (1.0) ANSWER:' ~ a. Keys used by Operations in normal performance of their duties. b. RPSbypasskeys(0.33)mayberemovedbytheReactorOperator(0.33) when needed during absence of the SS from the Control Room (0.34). [ COMENT: As detailed.in section~4.5.1 of Standing Order 0-26:- l. " Keys removed from hooks in Operations Key Depository for key lock-holde'rs_must be tagged with information as to where key is located when not-on assigned. hook." ~ This means that the keys may be removed from the Operation Key Depository without completion of the Key Log Sheet-(the tag is hung on the empty key slot in lieu of filling.out the key log sheet). Therefore, the answer should be revised to read as follows: L a. 1. Keys used by operations in normal performance of their duties - 2. Keys used in key lock holders Either answer is acceptable for full credit. ? 4' y}}