ML20135G402
| ML20135G402 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Duane Arnold  |
| Issue date: | 08/29/1985 |
| From: | Brockman K, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20135G401 | List: |
| References | |
| 50-321-OL-85-02, 50-321-OL-85-2, NUDOCS 8509180534 | |
| Download: ML20135G402 (21) | |
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ENCLOSURE 1 EXAMINATION REPORT 321/0L-85-02 Facility Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Facility Name: Edwin I. Hatch Facility Docket Nos.: 50-321 and 50-366 Replacement and Requalification examinations were administered at Edwin I. Hatch Nuclear Plant near Baxley, Georgia.
Chief Examiner: d/hM# '
F .2 7 - BS-pnE.-Ero(k, Date Signed Approved By: ~ ;- 4; ___3 /pf Bruce A. W11s f gf ate Signed Sunmary:
Replacement Examinations on July 15-17, 1985 Requalification Examinations on July 15-18, 1985 Written, oral, and simulator replacement / instructor certification examinations were administered, as required, to three candidates, all of whom passed.
Written and operating requalification examinations were administered to seven SR0s (seven written exams /three operating exams) and four R0s (two written exams, three operating exams); six of the SR0s and three of the R0s passed these exams.
(Two of the SR0 passes were on one section written examinations).
The performance on these requalification examinations (82% pass rate) will be combined with March 1985 results to attain an integrated appraisal of Plant Hatch's accelerated requalification training program. Final determinations ~will be addressed under separate cover.
8509180534 850909 PDR ADOCM 05000321 Q PDR i
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Enclosure 1 2 l REPORT DETAILS 4
- 1. Facility Employees Contacted:
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) H. Nix, General Manager, Hatch (E)
C. T. Moore, Training Manager, Hatch (E) 4 R. S. Grantham, Operations Training Supervisor (R/E) l D. Moore, Assistant Training Manager - Corporate (E) 1 D. Matherly, Simulator Instructor (General Physics) (R)
R. Rutan, Simulator Instructor (General Physics) (R)
] K. Elliott, Simulator Instructor (General Physics) (R)
M. Marlow, Simulator Instructor (General Electric) (R)
,' B. Smith, Simulator Instructor, Georgia Pcwer Company (R) i D. Giddens, Simulator Instructor Georgia Power Company (R) j i Note: "R" indicates present at examination review.
"E" indicates present at exit meeting.
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- 2. NRC Personnel:
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- K. E. Brockman, NRC i S. Guenther, NRC J. Munro, NRC M. King, EG&G P. Holmes-Ray, Senior Resident Inspector, Hatch (E) i
- Chief Examiner i
- 3. Examination Review Meeting j At the conclusion of the written examinations, the examiners met with
! facility representatives to review the written examination and answer key.
{ The following comments were made by the facility reviewers:
- a. SRO Requalification Examination l (1) Question #119 (5.01)
! Utility Comment: Phrasing of response "b" (correct answer) can be interpreted differently than intended. 50% equilibrium concentra-
. tion could be interpreted as 50% of the 100% concentration.
l 1 NRC Resolution: "50% equilibrium concentration" is standard terminology for the equilibrium concentration at 50% power. The
- question has been asked at numerous facilities without inter-l pretation difficulties. No change to Exam / Answer Key.
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Enclosure 1 3
!r (2) Question #198 (5.02)
Utility Comment: The knowledge needed by the SR0 is the Normal 4
Value of IXYFLG. He would consult the STA to find the meaning of an abnormal value. If he cannot specify on the test the meaning, he r'ceivese no credit for knowing that it is abnormal.
NRC Resolution: Knowledge of abnormal values without knowing what they mean is not necessarily appropriate. The essence of the lessons learned from Three Mile Island is that an operating staff ,
can not respond in a cook book fashion - the operators must be !
i knowledgeable of the bases / impact of abnormal responses. In this case, the operator should know that his Thermal Limit (MCPR) calculations are invalid. This is an integral part of the j operator's responsibilities. (Reference EIH Learning Objectives l L-RQ-677, EO #3, #6). No change to Exam / Answer Key.
1 (3) Question #211 (5.05) i Utility Comment: This is not an SRO function. It is performed by i the STA. The reference indicated in the exam key was not readily j available to the SRO.
l' NRC Resolution: See response to Question #198. The SR0 should be able to apply PCIOMR rules. The power ramp limit was provided as
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part of the question to preclude memorizing seldom used numbers.
l (Reference EIH Learning Objectives L-RQ-673, EO #5) No change to Exam / Answer Key.
(4) Question #240 (5.09)
- Utility Comment
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- b. Should also accept #2 Speed Limiter since both #1 and #2 will j come in and you can't determine which is causing the runback at Point 8. (#1 S.L. definitely completes the runback, but at Point B., you can't tell if its activated.)
- c. The Answer Key should give full credit for only saying " Void Collapse".
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- e. The Anwser Key should not require " Pressure didn't ... "
Alternative answers could be - Reactor - Pressure maintained 0 920 psig; water level didn't go below 0"; steam flow and/or feed flow pertubation; etc. ;
l NRC Resolution: l
- b. Graphs are specific enough to allow determination that only j #2 Speed Limiter is activated at Point B. (Total feedwater flow is still greater than 20% ) Note that specifying which j
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Enclosure 1 4 i
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j Speed Limiter is activated is not required for full credit; i however, if the examinee specifies, only #2 Speed Limiter 1
would be accepted for full credit, l c. Answer Key - asks for explanation of the concept, not a
{ quotation - no change to Answer Key.
{ e. Answer Key asks for justification of whether an isolation occurred. Any appropriate response is acceptable. Alternate
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> responses added to key. !
! (5) Question #294 (5.15) !
Utility Comment:
j c. The cause of the trip is not obvious by the information
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given.
l .e. Should accept for full credit that LLS actuates and controls '
i pressure.
i NRC Resolution: i t
{ c. The cause of the trip is not required by the answer key, j However, information is adequate to determine that only a low j level trip is possible. No change to Answer Key, t
- e. LLS actuation is already noted as an acceptable response. No change to Answer Key.
(6) Question #088 (7.03)
J Utility Comment: HNP-8008 has been revised to become 62RP-RAD-4 006-0, which redefines the types of RWPs and also states that t j original copies will be located in the HP offices. The question '
i is not representative of the present procedure.
I NRC Resolution: Acknowledged. Procedure modification since the j refere1ce material was submitted to the Commission invalidates the question as written. Delete from exam.
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- (7) Question #269 (7.16) 1
, Utility Comment: Per HNP-2-1938, the second part of the question j can be: (1) Wetting of the catalyst in the Recombiner; (2) Mal-
! function of the Preheater; (3) Malfunction of the Drain; as well
- as " Hydrogen Recombiner -Inoperability", which the Answer Key l states. First part of answer is satisfactory - insufficient steam flow to SJAE.
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Enclosure 1 5 ;
NRC Resolution: Answer key only requires stating that the recom-biner is unable to function properly.. Any condition reflecting this would be accepted. No change to Answer Key.
(8) Question #148 (8.04)
Utility Comment: Answer should not require that the pulled annun-ciator window be labeled with the appropriate annunciator control number,'just that it be labeled.
NRC Resolution: While it is felt that the operators should know what is the significance of all information available on the job, the question was not designed to require specifying the infor-mation on the label. Answer Key modified to not require this information.
(9) Question #242 (8.05)
Utility Comment: Question requires that Technical Specification limits be given - key requires Confirmatory Orders / Standing Orders as well, which was not explicitly asked for. No reference material provided for limits. Double jeopardy in that "b" couldn't be answered unless "a" was known.
NRC Resolution: Question asked for all limits to be listed -
since Confirmatory Orders carry the same compliance requirements as the Technical Specifications, the operators must know them to ensure regulatory compliance of the plant. The listing of the limits allows for partial credit in an " application" problem and is considered a valid evaluation item. No change to Exam / Answer Key.
(10) Question #251 (8.07)
Utility Comment: -Question requires student to recognize that SBGT train 28 is INOP. Thus, the question is double jeopardy in that if he does not see this, it will result in missing rest of question.
NRC Resolution: Question is an integrated one, requiring interpretation and application of Technical Specifications. It is acknowledged that if the SR0 can not recognize component inoperability, he can not properly. apply the action statements.
Since this is one of the key performance criteria for an SRO, it is considered appropriate and will continue on future exams.- It is not considered to be double jeopardy, No change to Exam / Answer Key.
Enclosure 1 6 :
I' (11) Question #253 (8.08) l Utility Comment: No correct choice for " Alert", per 63-EIP-014-0.
4 Answer expected on key for alert is not correct and is close to site definition. With no correct answer to choose from, response could be "1" or "2" for "b". Consider deletion or alternate response.
NRC Resolution: While responses "1" and "2" are similar, there is a substantive difference between the two (PAG violation, or not). f On this alone, the answer key would remain unchanged. However, the definition for " alert" was a direct quotation from the facility's GET Manual, and is, therefore, a completely valid choice. No change to Exam / Answer Key.
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- (12) Question #292 (8.15) r Utility Coniment
This requirement is tracked by Operations
- management and Operations training. It is not required knowledge ;
(memorized) for an SRO. Plant procedure HNP-200 specifies actions i
- for four months off-shift, but does not delineate reporting to the NRC, which is handled administratively by the Training Department.
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- NRC Resolution: 10 CFR 55 is specific in identifying that it is I
the licensee's (individual's) responsibility to notify the Commis-
- sion. The question is designed to determine if the candidate is
) familiar with this responsibility. .The spread of the distractors *
, is such that it does not require detailed knowledge to distinguish
! between the correct and incorrect response. No change to l Exam / Answer Key.
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- b. R0 Replacement Examination k (1) Question #203 (1.02) a ,
Utility Comment: Applying PCIOMR is performed by the STA at Hatch ,
and is not an operator _ function. Also, reference material was not !
i provided to the examinees. i i
4 NRC Resolution: The licensed operator is responsible to ensure !
i fuel integrity.is maintained. Simplistic application of PCIOMR is j considered appropriate knowledge expectation. The ramp rate limit r
- was provided as a NOTE to the question _ to preclude' the need for specific numeric memorization. (Reference Learning Objective i L-RQ-673, E.0. #5) No change to Exam / Answer Key.
, (2) Question #209 (1.03 & 5.03) i !
Utility Comment: This is STA level of knowledge. The question 4
tests two concepts: (1) location of APRM "C" AGAF on P-1, and (2) How to calculate power using AGAF. Examinee who does not know
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Enclosure 1 7 (1) will miss question which asks for power calculation. As a minimum, answer "a" should be accepted for partial credit.
NRC Resolution: This knowledge is at the operator level. A simple application of provided data is one part of the question; recognition of the appropriate data from a normally available reference is the other. The operator can not be half-right in maintaining the plant within its appropriate operating envelope.
Integrated application is required and seen as appropriate. No change to Exam / Answer Key.
(3) Question #213 (1.04 & 5.06)
Utility Comment: Question is not clear as to whether Curve B or Curve D is present concition. It would appear to be Curve B.
- a. Could be confusing based on above; i.e., operating point for full speed.
- c. Both methods will reduce power consumption - doesn't ask ,
which one does the most.
- d. Answer Key says "c" but if one assumes Curve "B" as the half speed curve, then "a" is correct.
NRC Resolution:
a/d. The potential.for confusion exists. Answer will be evaluated based upon whether candidate calls curve "D" the half-or full-speed curve. No change to Answer Key required.
- c. Question asks' for the action which will MINIMIZE power consumption. This, by definition, is the MOST REDUCED power.
No change to Exam.
(4) Question #243 (1.11)
Utility Comment:
- a. " Void Collapse" should also be accepted.
- b. Response should allow runback to #2 Speed-Limiter since both come in at about the same time. Can't tell from graph which starts at Point "B".
- c. Low level should not be required for full credit since examinee can't tell how low level is at point indicated.
- e. Response should allow "LLS activated" for full credit.
Enclosure 1 .8 NRC Resolution:
i a/e. Acknowledged - alternate wording for same concept. No change to Answer Key required.
3 b. At indicated point, total feedwater flow decreases below 20*(,; i therefore, Both #1 and #2 Speed Limiters are controlling. '
Answer Key modified to allow for either response.
- c. No reason was required on Answer Key; however, incorrect initiating conditions will not receive full credit.
(5) Question #264 (1.13 & 5.11) l Utility Comment: Difference between responses "a" and "c" was too subtle; i.e, the only difference is based on the diagonal adjacent i rod at position 48 vice 00. Recommend deletion or accepting I responses "a" or "c".
NRC Resolution: Differentiation of flux profile based only' on diagonal rod position is Nuclear Engineer level of knowledge. ,
Answer "a" or "c" shows recognition of flux response to a shallow l rod pull - both answers accepted. Answer Key modified. !
(6)' Question #265 (1.14 & 5.12)
Utility Comment: Response "b" is also appropriate since Boron-10 has a greater absorption cross-section for thermal neutrons than Hafnium.
NRC Resolution: Acknowledged. Answer Key changed to accept l responses "b" or "d". !
! l (7) Question #278 (2.06 & 6.10) i j Utility Comment: Answer could be true or false depending upon l
, assumptions, since the question is not explicit. Both SBLC pumps can.be run simultaneously from local control station, but not from control room.
NRC Resolution: While the utility training material says that !
simultaneous operation. of both SBLC pumps is precluded by inter-lock, it can be accomplished by local operation. Since the ,
True/ False statement was p'esented r as - an absolute, only one i response, FALSE, is' correct. Answer Key modified based ~upon EIH Drawing H-27525.
(8) Question #284 (2.10)
Utility Comment: Answer key should be changed to allow PSW pump-indication to be either Closed (RED) or Open (GREEN). Since the l PSW pumps load shed on' LOSP to the Bus (0 pen / GREEN), but will t
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Enclosure 1 9 restart (Closed / RED) once the Bus is reenergized by its EDG (Time
= 30 sec), either response should be accepted.
NRC Resolution: Analysis of the indication circuity of the PSW Pumps shows that they will, in fact, display Open (GREEN) upon LOSP. This -is a correction to the Answer Key. The question, however, poses that the pumps have a " LOSS of their associated 4160 Vac power supplies". This is straightforward in depicting a total loss of power.and, therefore, only the Open (GREEN) response is correct. Answer Key modified.
(9) Question #288 (2.12)
Utility Comment: "... and thus cooling water flow is low "should not be required as part of the answer for full credit since it is t j a "given" in the question.
NRC Resolution: Grammatical specifics are not required for ~ a written response. If-the concept is explained, full credit will be given. No change to Answer Key required.
- (10) Question #289 (2.13)
Utility Comment: Answer "a" should also be accepted since neither unit is specified.
t NRC Resolution: Acknowledged. Neither unit was specified.
Answer "a" or "c" will be accepted. Answer Key modified.
(11) Question #296 (2.16)
Utility Comment: The question is not based on'a Learning Objec-tive. The answer key should also accept, "Above the core plate" and the " core spray injection piping downstream of the injection valve" as full credit descriptors.
NRC Resolution: The question is based upon Learning Objective L-RQ-739, E.O. #2. Again, specific wording is not required for full credit if the concept discussion is accurate. In this case, the Answer Key was modified to indicate the more precise loca-tions.
(12) Question #084 (3.01)
Utility Comment: The Answer Key should be . modified to accept
" Energized" for the Red Light indication upon high' pressure.
Since the question did not specify if the SRV was part of LLS, it. '
could indicate energized.
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Enclosure 1 10 NRC Resolution: Acknowledged. The question was intended for indication at the high pressure relief setpoint, meaning mechan-ical actuation. If the examinee indicates an LLS valve, the response " Energized" will be accepted. Answer Key modified. .
(13) Question #223 (3.03)
Utility Comment: RWM groups have changed significantly such that this condition could never occur, nor are RWM groups 3 & 4 limits "00" and "48". RWM Group 3 limits are 00-04 and Group 4 from 04-08. Question should be deleted because it is impossible to have the same control rods (Group 3 & Group 4) at two different positions. If it is assumed .that these are RSCS Groups, then the condition would only be possible if the RWM were bypassed, then reinitialized at these conditions. If this is assumed, -the answers should be:
! a. 03/22-51/46-55/Any GP #6 Rod
- b. 07/18-03/46-55/34-27 The above answers should be accepted.
NRC Resolution: The question presents a hypothetical situation.
Limits are given, and adequate specifics concerning these RWM Groups are provided. The examinee is required to apply the given to the RWM logic and describe how this would be indicated in this case. This application question precludes memorizing specific groups and pull points and investigates system responses generically. It is seen as valid and precise. No change to
- Exam / Answer Key.
(14) Question #244 (3.09 & 6.04)-
Utility Comment: Answer "b" is correct. Selection of an A-34 rod
, is not required, nor is rod position of A-12 rods material. Only A-34 must be selected.
, NRC Resolution: While selection of an A-34 rod is not required, if all A-12 rods do not indicate fully withdrawn, a select block occurs and the RSCS backlighting (amongst other indications /
capabilities) will not occur. Correct response is "a".
,. (15) Question #283 (3.13 & 6.14)
Utility Comment: Question had to be changed from M/A Station "A"
'to "B" by the examinee. If change was not made,-answer would be
" Remains Same" and "B Individual Controller".
d Enclosure 1 11 NRC Resolution: Pen and ink change was made by examiner on each exam prior to exam administration. No change to Answer Key.
(16) Question #298 (3.14) 1 Utility Comment: Type of gamma signals was not asked for (decay
! and/or background). Delete the above meationed items from key.
NRC Resolution: Specific wording is not required if a concept is adequately explained. In this case, an examinee must address
, gammas which are not proportional to power to adequately explain the basis for discrimination. No change to Answer Key required.
(17) Question #299 (3.15)
Utility Comment: Delete the question because the correct answer (TCV, TSV, IV, ICV) was not listed.
- NRC Resolution: While answer "b" did not specifically say IV's, the descriptor of "all control valves" and the " main stop valves" is considered adequate to elicit the correct response. IV's will be added parenthetically for future usage. No change to Exar/ Answer Key required.
- i. (18) Question #017 (4.02)
Utility Comment: HNP-8008 has been deleted and replaced by three pVP-procedures. There are no longer regular, routine, and blanket RWP's. They have been replaced by General and Specific RWP's.
The question should be deleted.
NRC Resolution: Procedure was deleted af ter material was sub-l mitted to NRC. New procedure invalidates exam item as presented. !
l Question deleted.
l (19) Question #090 (4.03 & 7.04)
Utility Comment: The question 'should only ask for two criteria.
(There are NOT three criteria). The answer key should be changed to read: -
Potential hazard to equipment exists 5
~ Potential hazard to personnel exists.
NRC Resolution: The glossary of terms for Procedure 10AC-MGR-003-0S,
- p. 47 provides a third criteria for a CAUTION - A danger to public health and safety exists. This is unique to personnel and equip-ment danger. No change to Exam / Answer Key.
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Enclosure 1 12 (20) Question #108 (4.05 & 8.03)
Utility Comment: HNP-507 was replaced by DI-0PS-05-1084. Infor-mation tags are no longer specifically covered in this procedure.
The question does not apply now and has no correct answer.
NRC Resolution: New reference was not supplied to Commission.
Review of DI-0PS-05-1084 and the current conduct of operations shows that Information Tags are covered by this new procedure and are subject to specific controls and guidelines. However, the new guidance invalidates the question as written, due to two 4
inadequate distractors. Delete from exam.
(21) Question #227 (4.07 & 7.05)
Utility Comment: HNP-2163 does not direct operator to ENGAGE turning gear; therefore, there is no clearly correct answer.
NRC Resolution: Step #4, HNP-2163 addresses operator uctions when the Turbine goes onto the Turning Gear. This provices adequate direction. No change to Exam / Answer Key.
(22) Question #239 (4.08)
Utility Comment: The GET handbook has been revised with the reference on page 33. Per 60AC-HPX-004, Attachment 3, the minimum required Anti-C's depends on whether the reason for entering the contaminated area is for Inspection and Surveillance OR for work in progress.
! For Inspection and Surveillance only the minimum Anti-C 1
requirement is Shoe covers, rubber' overshoes, cotton a,,nd rubber gloves.
For work in progress the minimum Anti-C requirement is Full suit of anti-C's, tape all openings.
This assumes contamination levels of 1000 dpm/100 cm2 to 10,000 dpm/100 cm2 If contamination levels are higher the minimum required Anti-C's requirements become even more conservative.
Since "whether or not work was in progress" OR " contamination levels" were not addressed in the stem of the question an alter-nate acceptable answer should be " full ' anti-C's with tape on all openings".
t Also the reference used in the answer key was not given_ in the stem of the question therefore the examinee was free to answer it in accordance with 60A-HPX-004 attachment 3.
Enclosure 1 13 Another alternative would be to delete the question.
NRC Resolution: If examinee specifies that his response is for Work in Progress, the alternate response will be accepted. Answer Key modified to allow for alternate response.
(23) Question #245 (4.09 & 7.07)
Utility Comment: Response "a" states when exiting any "contain-ment" area - should read any " contaminated" area.
NRC Resolution: Acknowledged - typographical error. Answer Key 'l modified. '
(24) Question #247 (4.10 & 7.09)
Utility Comment: The Answer Key should accept the alternative answer of "to prevent overtorquing or failure of the suction or
, discharge valve actuators.
NRC Resolution: Acknowledged. The end result of the piping overpressurization (all that answer key required) displays 3
knowledge beyond that requested and is _ allowed. Answer Key modified to allow for more indepth response.
(25) Question #248 (4.11 & 7.10)
Utility Comment: Although the Answer Key response appears in the same CAUTION statement (HNP-1010, p.11), this is not the reason 4
why notch-and wait is employed as criticality is approached.
The key should also accept:
Prevents excessively short periods when criticality is achieved, OR ,
I Produces a controllable period and, therefore, a controllable I power assumption.
l NRC Resolution: The end results (alternate responses) of the i Answer key response are acceptable, in that they show greater l knowledge than requested. No change to Answer Key _ required. ;
l (26) Question #266 (4.13 & 7.13)
Utility Comment: No procedure was referenced in the stem of the !
question. -The manual ADS initiation requirements have been ;
l changed, and should read: -l If ADS cannot be automatically initiated, and:
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Enclosure 1 14 (1) HPCI, RCIC, CRD, or condensate and feedwater are unavailable or cannot maintain reactor water level.
(2) Reactor water level < -121.5" (3) Low pressure water is available (CS or RHR)
(4) Reactor Pressure >350 psig.
NRC Resolution: More detailed response is acceptable. Answer Key response summarized above requirements. No change to Answer Key required.
(27) Question #272 (4.16)
Utility Comment: Procedure 10AC-MGR-003-0S, on SR0ing proce-dures is not in effect, -so some examinees may answer per HNP-9 requirements which are currently in effect; therefore, an alternate answer should be "a".
NRC Resolution: Procedure 10 AC-MGR-003-0S is in effect (4/6/85, Rev. 2). Both this procedure and HNP-9 cover SR0ing procedures and it is essential the operator knows the disparate guidance. No change to Answer Key.
, c. SRO Replacement Examination (1) Question #564 (5.01)
Utility Comment:
1 (a) Question is not plant specific.
(b) Core flows shown will confuse student since they don't ,
correlate to plant values.
(c) Low-low set is not accounted for.
NRC Resolution:
(a) The material provided is different in some aspects from E. I.
Hatch; however, the specific transient points to be identi-fied should be known by an SRO. In addition, a " plant specific" transient would have been written if " plant specific" material had been included . in- the exam material, as was provided for the requalification exams. No change to Exam / Answer Key.
(b) The exact values are.somewhat different but_the_ purpose of transient evaluation is-to identify the most likely cause of a particular event, regardless of indicated values, i.e. The s trace for a scram, recirculation pump trip, core voiding is h
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Enclosure 1 15 representative of Hatch. It is agceed that the specific cause (setpoint) may be not easily seen from the parameter scale. No change to Answer Key required.
(c) Agreed; however, no questions are asked about the " low-low set" area on the plots. No change to Answer Key required.
(2) Question #565 (5.02)
Utility Comment:
(a) Question is not plant specific.
(b) Core flows are confusing to student since not plant specific.
(c) Part a - voiding of core should get full credit.
(d) Flux scram setpoint never reached.
r NRC Resolution:
(a) The material provided is different in some aspects from E. I.
Hatch; however, the specific transient points to be identi-fied should be known by an SRO. In addition, a " plant specific" transient would have been written if " plant specific" training material had been included in the exam :
material. 'No change to Exam / Answer Key.
4 (b) The candidate was given that both recirculation pumps had tripped and was the cause of the transient. Because the ;
recirculation pumps are known to be tripped, the candidate ;
would not misinterpret the referenced point as a recircu- !
lation pump trip due to non plant specific values. No [
change to Answer Key required, [
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(c) Agreed, since " decreasing" recirculation flow is given in question.
(d) Agreed. The student only needs to identify the " scram", not >
a "high flux scram". However, an incorrect cause will not be '
acceptable for full credit.
(3) Question #562 (5.05) :
Utility Comment:
(a) Question not straight forward - wording concerning "directly proportional". Test math via knowledge of concept. ;
(b) Part "d" "same rod movement" vice "same reactivity" could i lead one to answer "a".
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Enclosure 1 16
- NRC Resolution
1 (a) Disagree, an SR0 candidate should know the general effects of source strength on neutron count rate. No calculations were i required by this question. No change to Exam / Answer Key.
(b) Comment not applicable as candidates were instructed to assume "same reactivity". However, any reasonable assump-tion on part "d" does not lead to anwer "a" being correct.
(4) Question #570 (5.07)
Utility Comment:
(a) Students not required to calculate NPSH in curriculum, but required to predict affects.of changes.
(b) No formula provided.
NRC Resolution:
(a) The question provides all parameters in correct units (psia) with required steam tables for SAT temperature to SAT pres- i sure conversion. _This question is SRO konwledge. No change to Exam / Answer Key.
(b) No formula required for this question. Only steam tables
- (provided) and application of the ' definition of NPSH to arrive at the answer.
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'(5) Question #572 (5.09)
Utility Comment: Answer key requires why generator output increases, which is not asked by the question. Revise key to answer the question. j NRC Resolution: Although the student does not need to explain specifically why generator output increases, he does need to explain that delta power increases in the reactor will be greater than the generator causing an efficiency decrease. No change in Answer Key required.
, (6) Question #574 (5.11)
Utility Comment:
(a)- Installed sources are required because all the intrinsic are
-too small.
(b) Answer 2 or 3 could be correct depending on interpretation of BOL and power history.
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Enclosure 1 17 4
(c) Correct answer not given. 0 EOL core avg. exposure is < 20
. GWD/T so correct answer is SP. Fission or CM 242. Also, time after shutdown not specified, so answer 2 may be correct.
- NRC Resolution:
(a) Comment not accepted. This question addresses intrinsic i sources only. No change to Exam / Answer key.
1 (b) Agreed. Since question did not specifically define "BOL".
Answer 2 or 3 will be accepted.
(c) From the list provided, CM-244 is the most correct answer per Hatch reference material. Answer 2 is also acceptable since time after shutdown is not given.
(7) Question #579 (5.16)
Utility Comment:
(a) Correct answer not given.
(b) Part B is math that would. not normally be done by anybody ,
other that testing a concept. Deletion recommended.
NRC Resolution:
(a) Agree. Typo 1.63 vs. correct answer 1.68. Since no correct choice was provided, question deleted.
(b) Disagree. This is a simple exercise in locating two numbers from a computer P-1 printout. The definition of. efficiency is SRO knowledge; no change to Exam / Answer Key.
- (8) Question #580 (6.01)
- Utility Comment
- Should also accept answer "a" for Part II due to the initial " swell" of RWL (due to SRV opening) could possibly cause a turbine trip.
1
, NRC Resolution: Disagree. No information supporting facility comment was provided. EHC will reduce turbine steam flow to maintain set pressure, reduced steam flow will cause feed pump speed decrease. Any . reactor vessel level increase will cause
, additional signal to decrease feed pump speed. No change to Answer Key, s
Enclosure 1 18 l
-(9) Question #581 (6.02)
Utility Comment:
(a) Should give full credit for answer key answer "B.1".
(b) Should also accept the answers listed in exam key.
+
NRC Resolution:
(a) Agree. Component list in question was inadvertently -
shortened. Full credit will be given if "B.1" (reactor water sample cooler) is listed.
(b) Disagree. " Reactor water sample cooler" is the only correct ,
answer of those provided. Second answer will be disregarded.
(10) Question #582 (6.03) i Utility Comment:
(a) Should also accept 2# DWP (Unit 1) and 1.63# DWP procedure
- setpoint (Unit 2) and -116.0# RWL procedure setpoint (Unit 2
& 1).
- (b) Answer key is incorrect. LPCI initiation signal is not required to effect Drywell Spraying.
NRC Resolution:
(a) Question did not stipulate Unit 1 or Unit 2, 2# (Unit 1) or i 1.85# (Unit 2) will be accepted. No justification /documen-tation provided to change values to 1.63# (Unit 2) and
-116.0# RWL. ,
(b) Agree, per L-RQ-741 "1". Not required as question is only concerned "with LPCI" initiation signal present. Answer key modified. .
l (11) Question #583 (6.04)
Utility Comment: Answer "a" should be accepted for HNP Unit 1.
NRC Resolution: ' Agree. Unit I and Unit 2 P&ID provided. Answer "a"'or "c" will be correct.
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Enclosure-1 19 (12) Question #586 (6.07)
Utility Comment:
(a) Should also accept initiation signals for RPT: TSV < 90% open TCV Low oil pressure (< 600 psig)
(b) Should also accept components activated for RPT: RPT breaker ...
NRC Resolution:
(a) Agree. Answer Key modified.
(b) Agree. Answer Key modified.
(13) Question #587 (6.08)
Utility Comment: 'The question did not ask to " define" a generator runback; therefore, the answer key should delete: "A turbine runback is a rapid reduction'of generator load to 24% (.5)".
NRC Resolution: Disagree. The definition is only one way to
" describe" the plant response to a run back. The candidate may use different words to describe the event'. No change to Answer Key required.
(14) Question #589 (6.10)
Utility Comment: Part B:
- 1. Charcoal filter --+ also : removes radiation particulate (Vol. 5.3.3.6).
- 2. Blower --+ also accept b, provides cooling through the
" alternate" SBGT train. (Example - only one SBGT train operating).
NRC Resolution:
- 1. Disagree. Vol. 5.3.3.6 does not support comment. No change to Answer Key.
- 2. Agree per Vol. 5.3.3.2. Answer Key modified.
(15) Question #590 (6.11)
Utility Comment: _ Should also accept answer "a" because the relay K752A/B performs this function for relay K7A/B.
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Enclosure 1 20 i
l NRC Resolution: Agree, per L-RQ-702, answer "a" or "c" will be accepted. Answer Key modified.
(16) Question #593 (6.14)
Utility Comment: Part A should be deleted because the RBM no
- longer uses APRM for gain adjustment.
NRC Resolution: Design Change for RBM (see L-RQ-719) invalidates the test item. Question deleted.
4 (1.) Question #595 (7.02) l Utility Comment: The question does not specify whether the auto actuated system was a result of manual S/U or automatic S/U.
If a manual S/U is performed on an auto actuated system, answer "a" is also correct.
f NRC Resolution: Disagree. Answer "a" is a condition of HNP-14.
No change to Answer Key.
(18) Question #608 (7.15)
Utility Comment: The answer key should accept either " generator j synch" or "after turbine roll up". Procedure just requires them i
to be in service prior to 25% MWT and they should be placed in service after heatup is complete. Ref: HNP-2-1001, Purpose.
NRC Resolution: Disagree. Hatch procedure HNP-2-1605 states "...
are placed in service just after synchronization (above 10%
load)." No change to Answer Key.
l (19) Question #609 (7.16)
, Utility Comment: This procedure (HNP-8008) is no longer used -
! Ref: 60AC-HPX-004, Section 8.6 RWP, answer a, b, and d are '
correct.
i NRC Resolution: Acknowledged. Procedure modification since the reference material was submitted to the Commission invalidates the question. Delete from exam.
(20) Question #612 (8.02)
! Utility Comment: HNP-503 Ref: 8, Page 2. Answer b is also I j correct; should accept either answer b or c.
f NRC Resolution: Agree. Acceptable responses will be "b" or "c".
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Enclosure 1 21 (21) Question #613 (8.03) i Utility Comment: Due to variation in psig and psia and the "or" between 860 + 10% - for the <25% power limit. Three possible
- answers exist, "a" and "b" also " incorrect".
NRC Resolution: Agree. Question deleted'from exam.
(22) Question #619 (8.09)
Utility Comment: The a part is SAT. Gray area on part b. Could possibly select 6.9.1.8.a as the answer.
4 NRC Response: . Agreed. Technical review of the question supports the utility opinion that .the. scenario as presented is best i supported by T.S. 6.9.1.8.a. Answer Key modified to reflect this
- (7 day report) as the proper response.
(23) Question #623 (8.13)
Utility Comment: T.S. 3.6.1.6 requires hot S/D in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold S/D in following 24-hours. Correct answer should be:
l Hot S/D 0200 7/16/85
- Cold S/D 0200 7/17/85 l
NRC Response: Agreed. Answer Key modified.
1 (24) Question #628 (8.17)
Utility Comment: Answer should be "c" which is 6 and 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
They selected no further action required, based upon inability to meet auto-swap surveillance criteria.
i NRC Resolution: Disagree. Operability of HPCI only requires
- Suppression Pool suction path. Thus, there is no basis to define HPCI as INOPERABLE and enter LCO actions. No change to Answer Key.
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- 4. Exit Meeting At the conclusion of the site visit the examiners met with representatives 4
of the plant staff to discuss the results of the examination. Those indivi-duals who clearly passed the oral examination were identified.
~
There were no generic weaknesses (greater than 75 percent of candidates giving incorrect answers to one examination topic) noted during the oral examination.
The licensee did not identify as proprietary any of the' material provided to or reviewed by the examiners.
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