AECM-86-0031, Comments on NRC Written Reactor & Senior Reactor Operators Exams Administered to Nine Candidates on 860110,per Request

Comments on NRC Written Reactor & Senior Reactor Operators Exams Administered to Nine Candidates on 860110,per Request

ML20138C544
Person / Time
Site:	Grand Gulf
Issue date:	01/25/1986
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20138C531	List: AECM-86-0031, Comments on NRC Written Reactor & Senior Reactor Operators Exams Administered to Nine Candidates on 860110,per Request ML20138C527 ML20138C536
References
AECM-86-0031, AECM-86-31, NUDOCS 8604020528
Download: ML20138C544 (5)

Text

- -

ENCLOSURE 4 MISSISSIPPI Helping POWER & LIGHI.lQlg' PANY Rulld Mississippl.

P. O. 8 0X 184 0. J A C K S O N. MIS SIS SIP PI 39215-1840 January 28,1986}6/"  : Fi2 : 01 NUCLE AR LICEN5tNG & SAFETY oEPARTAAENT

.u; RGN II U. S. Nuclear Regulatory Commission J.iLANTA, GA.

Region II 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Actention: Dr. J. Nelson Grace, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 -

File: 0260/L-860.0 NRC Examinations AECM-86/0031 On January 10, 1986, NRC examiners gave a written examination to 9 Grand Gulf Nuclear Station (GGNS) Unit 1 candidates for NRC Operator and Senior Operator Licenses. Upon completion of the examination, a copy of the examination was supplied to Mississippi Power & Light (MP&L) with the request that the exam be reviewed and any appropriate comments be furnished to the NRC.

The following comments are supplied pursuant to that request:

REACTOR OPERATORS EXAMINATION t

1. Question 1.14 - Interpretation of data provided by OD-6 is not an objective of the training program (or RO's nor is it included in the duties of the Reactor Operator. This task at GGNS is assigned to the Shift Technical Advisor. OD-6 is only mentioned in the Mitigating Core Damage lesson text (pages 72, 74 and 76)

$g as a possible source of information.

<M o Additionally the GGNS OD-6 option 1 does not include the same

$s5 information that is provided on the copy of the Browns Ferry-2 mo OD-6 option 1 included in the examination. Candidates should not g be expected to respond to a question requiring interpretation of no data to which he has not been previously exposed. Therefore we

@ recommend that Question 1.14 be deleted from the examination.

o Copies of the MCD Lesson Plan, MCD Lesson Text, OD-6 option 1 and om OD-6 option 4 are included for your information (Attachment I).

N> 2. Question 1.19 - Question A required calculation of girculating waterflowrateusingasteamflowrateofg.0x10 LBM/IIr.

Answer key used steam flow rate of 6.6 x 10 LBM/Hr in the calcu-lation. Usingthesteamfgowrateprovidedinthequestionthe answer should be 2.01 x 10 LBM/Hr. We recommend that the answer k e:, be cl.anged to reflect this answer.

J16AECM8M1. -

Member Middle South Utilities System

(

e AECM-86/0031 [

• Pcg2 2 i

3. Question 2.06 - Part B of answer key _ required the necessary conditions for the standby filter train to restart. The question only requested the effects of placing the fans to stop after the i mode select switch is in'" standby" and the manual initiation reset switch is taken to reset. The answer should be, "the SGTS Train A will stop". We recoemend that the answer key be changed appropriately.

4. Question 2.09 - The answer key stated the correct response was item D. According to SOI 04-01-R21-1 (Page 11) and GGNS Electri-cal Prints (E1226 and E1116), Component Cooling Water Pump "B" will not auto start, but can be manually started by the Operator on ESF power after the bus is re-energised. Therefore, the more correct answer abould be item "C". A copy of the 301 and electri-cal prints are attached for your reference (Attachment II). We -

recommend that the answer key be changed appropriately. '

5. Question 2.11 - The answer key stated the correct response is item D. In accordance with GGNS lesson plan OP-C41-8-01 (Page 15 -

of 25) and GGNS Electrical Prints (E1169-05), SBLC pump "A" will start from the control room if either F001A or F031A are full open. Therefore the more correct answer is "C" - Valve F001 does not open and SBLC pump "A" starts. A copy of the appropriate electrical prints and lenson plan is attached for your reference (Attachment III). We recommend that the answer key be changed appropriately.

6. Question 2.18 - Part B requested the awaminee to describe the two (2) system conditions which are indicative of excessive MSIV leakage and their resultant automatic action (s). In accordance

' . with lesson plan OP-E32-501 (page 10 of 24) F001A, F002A and F003A close if high pressure is received (> 5 pois) between MSIV's af ter one (1) minute. Answer key stated only F001A and F002A closed after receiving a high pressure signal ( >5 paig) after one '

minute. The answer key is correct in that after 13 minutes a high leakage flow (> 22 SCFH) sir,aal will shut the F001A and F002A valves. A copy of the lesson is attached for your reference (Attachment IV). We recommend that the answer key be changed to reflect the F003A valve closure.

7. Question 3.06 - Answer key stated the correct response as item D. In accordance with GGNS Alarm Response Instructions (04 1H13-P680-3A-BS) for "Recire Pump A/B Seal Stage Plow Hi/ Low" Alara, another possible cause is the failure of No. One (1) seal. i Therefore the correct answer could be item A or D. A copy of the appropriate Alarm Response Instructions is attached for your i reference (Attachment V). We recommend that the answer key be changed appropriately.

^

.. '86012702 j

, AECM-86/0031  ;)

Pegs 3

8. thestion3.11-PartArequestedthe1,cadReferenceDemand(in MW's) that is required for the IPC signal to become the minimum signal to min. 1. Answer key stated 500 MW. Calculations show 1 the answer to be 522 MW. l i

Speed Demand = 1809 RPM, therefore, 1809 RPM TE96 RPM " . ,

I Speed demand and load reference demand are an additive signal to min. gate 2. IPC- speed demand equals the smallest valve load

. reference has to be to make the IPC signal the minimum signal. q l

501 ,10% = 401

.40 x 1306 M1 = 522 MW ,

Allis-Chalmers power system turbine general instruction manual chapter 5 (operating instructions) is included for your reference (Attachment VII). Page 17 of-chapter 5 explains the reason for using 1890 RPM in the above problem. We recommend that the answer key be changed to include this value as an acceptable answer.

9. Question 3.13 - Part B requested the three (3) SCRAM functions which become effective when mode switch is taken to run and include their setpoints. One answer is "APRM high power-flow (clasped < 118%). In accordance with GGNS lesson plan number OP-C51-4-501 (page 25 of 33), a more correct answer would be APRM upscale neutron flux (1181) in addition to Ex vessel high water level (53.5") and MSIV closure ( < 94% 70 x 3 lines). A copy of the lesson plan is attached for your reference (Attachment VIII).

s. We recommend that the answer key be changed appropriately.

10. Question 3.15 - Answer key stated all IRM rod blocks are not in effect only if the respective IRM channel is bypassed. The answer

, key also stated the IBM downseale trip setpoint is 3/125 of scale.

In accordance with lesson plan no. DP-C51-2, (page 18 of 25), the IRM rod blocks are also not in effect when the reactor mode switch is placed in "run" position. Also the IRM downscale trip setpoint is 5/125 of scale. A copy of the IRM lesson plan and appropriate page of tech specs is attached for your reference (Attachment VI).

We recommend that the answer key be changed appropriately.

1 l

J16AECM860 2702 - 3

, AECN-86/0031 1

. Pc3e 4 l

- T

. SENIOR REACTOR OPERATOR EXAM

1. Question 5.12 - Same comments as the second paragraph for question 1.14 on the R.O. Exam.

2. Question 6.07 - Same comments as question 2.06 on the R.O. Exam.

3. Question 6.09 - Same comments as question 2,09 on the R.O. Exam.

4. Question 6.11 - Same comments as question 2.11 on the R.O. Exam.

5. Question 6.15 - Same comments as question 3.13 on the R.O. Exon.

i

6. Question 6.16 - Same cossents sa question 3.15 on the 1.0. Exam.  !

i

7. Question 8.12 - The question directs the candida'te to " Evaluate

• I for each of the four (4) TS . leakage LOO limits....." but doce not .]

supply him/her with directions as to how the response should be .

recorded. -The responses could range from a simple statement such i as " Evaluation completed" to a detail essay which includes the l necessary anthematical calculations. The answer key requires a '?

^

response as though the question was worded, " List the four (4) TS leakage LCO limits.....and indicate whether the limit was exceed or not". We recommend that due to the phrasing of the question '

the candidates response should be graded based on his presenting evidence that he conducted an evaluation and whether his evalua-

• tion was correct even though it does not include all the informa-tion presently included in the answer key. That is, full credit .

should be given for the response " unidentified leakage (2 gym lI increase 0400-0800) - exceeded" in that this indicates an evalua-s , tion was conducted and only this specific technical specification limit was exceeded. By implication the others were not. Other-wise we recommend that the question be removed from the examina- ~

t tion. 4

'1 Should you require any further informatioh concerning these comments, please contact Mr. Gary Lhamon of the GGNS plant staff.

Yours truly,

, F. Dale Director LFD:bms Attachments cc: (See next page)

J16AFCr4 0l?70. -:

, t J l 4 ABCM-86/0031 .

Pasa 5 cc: Mr.-J. B. Richard (w/a) l Mr. O. D. Kingsley, Jr. (w/a) i Mr. R. B. McGehee (w/a)

Mr. N. 8. Reynolds (w/a)

Mr. B. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Bruce Wilson (w/s) l U. S. Nuclear Regulatory Commission l Region II l 101 Marietta Street, NW, Suite 2900 l Atlanta, Georgia 30323 n Mr. James M. Taylor. Director (w/a)  !

Office of Inspection & Enforcement U. 5. Nuclear Regulatory Commission '

i

. _ _ . __ .__. Washington, D.C. -.20555 ... __ ..-_.___ _ . . _ _ _ _ . _ . _ _ _ _ _ _ . . . _ _

. __ h-J t

~

h i

J v

k 9

r

]

l l

J 16ATCM MO! J-( .' '

-