ML20209E184

Submits Followup Comments Re Reactor Operator & Senior Reactor Operator Written Exams Administered on 870209

ML20209E184
Person / Time
Site:	Surry
Issue date:	02/12/1987
From:	Friedman A, Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20209E169	List: ML20209E164 ML20209E172 ML20209E184
References
NUDOCS 8704290450
Download: ML20209E184 (6)

Text

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, . Enclosure 3 m

4 i February 12, 1987 4

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Mr. John F. Munro Operator Licensing Section Division of Reactor Safety Docket Nos. 50-280 Region II 50-281 U. S. Nuclear Regulatory Commission License Nos. DPR-32 Suite 2900 DPR-37 101 Marietta Street, N. W.

l Atlanta, Georgia 30323 j

Dear Mr. Munro:

VIRGINIA ELECTRIC AND POWER COMPA.NY SURRY POWER STATION UNIT NOS. 1 AND 2 WRITTEN LICENSE EXAMINATION COMMENTS In accordance with NUREG-1021, Section ES-201, the following comments are submitted concerning the Reactor Operator and Senior Reactor Operator written examinations administered at Surry on February 9,1987.

4 REACTOR OPERATOR EXAMINATION QUESTION # COMMENTS l 1.04 Answer (3) should not specify cold leg temperature. Basis in Tech Specs (Page-2.1-2) says reactor coolant temperature and the thermal hydraulic curve specifies Tave.

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Reference:

Tech Specs 2.1-2 and Figure 2.1-1.

1.08(b) Answer should be increases. In a core that is several

cycles old, the buildup of Pu-240 causes FTC to become more negative over core life.

Reference:

Lesson Plan ND-86.2-LP-1, Page 1.16.

1.13 Question asked for 3 conditions for indications of criti-cality. Having a positive SUR means the power is increas-l ing; therefore, power increasing should not be required as indicated in the Answer Key. Acceptable answer should be

Start-up rate is positive and constant with no outward rod ,

motion.

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o Mr. J. F. Munro Page 2 i 1.14 Answer (2) could also be stated "far enough into the inter-mediate range where compensating voltage problems will not

! affect the indication."

4 1.18 Answers 'A' and 'C' imply the same answer; both should be accepted.

1.20 Add the following to the Answer Key:

- 1) Shutting discharge valve prior to starting a pump.

2) Slowly initiating flow to a system.

2.06 Answer Key does not reflect correct answer. Answer should be as follows:

A) 1) g (1J) " A (I) - 1J

2) b (1B1) Heater B (II) - 1B1

3) c (1C1) Groups < C (III) - 1A1

4) f (1H) D (IV) - 1C1

_ E (V) - 1H j B) a (1A1)

Reference:

ND-88.1-LP-3, Page 3.11.

l' 2.14 Answer Key indicates a description of each bypass flow path when only a list of the bypass flow paths was requested.

The following answer should be accepted:

Head Bypass Nozzle Bypass Baffle Bypass Thimble Bypass 2.19(a) Add the following answer to part (A):

Control Room chillers.

Reference:

hT-89.5-LP-2, Page 2.13.

! 2.21 Question asked why an elevated pH is established in the con-tainment sump. Answer for iodine removal should be removed from Answer Key since it is a reason for adding NaOH, not for establishing an elevated pH. Answer number (2) should j be the only required answer.

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Reference:

ND-91-LP-5, Page 5.13.

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o Mr. J. F. Munro Page 3 2.22 Ambiently heating up RHR should not be an answer. Alternate acceptable answers should be:

1) Prevent overpressurization by providing a letdown flow path.

2) Allow RHR heatup prior to placing it in service.

2.23(a) The components listed cannot be placed in any logical order because part of the components deal with the rod control power supply and part of the components deal with the logic signal generated for moving the rods. Any type of sketch or drawing and/or explanation showing that they cannot be arranged should be an acceptable answer.

Reference:

ND-93.3-LP-3, Transparency 3.3, 3.5, 3.18.

3.06 Answer (a) should also be accepted as a correct answer.

NOTE: For the RWST there is no differentiation between a low or low-low setpoint for RMT swapover.

Reference:

ND-91-LP-3, Page 20.

3.09 Anytime an SI (CLS) signal is generated (Train A or B), both trains of SI (CLS) will be initiated. For this reason, Training does not require RO/SRO Candidates to specify which Train (A or B) of the SI (CLS) signal operates what equip-ment. Specifying Train B as a start signal for #3 EDG should not be required.

3.10 Answer (4) should be changed to accept the following:

1) Accumulator discharge MOV open signal

2) Pzr PORV close signal

3) SI block / unblock signal Each of these signals should be accepted as one of the five required answers.

Reference:

ND-93.3-LP-12, Transparency 12.4.

3.11 Delete answer #3; add the following:

Limit hot channel factors (by providing more even flux distribution).

Reference:

ND-93.3-LP-3, Page 26.

l 3.13 Delete (2 loops) from Answer Key for Pzr lo pressure.

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Mr. J. F. Munro Page 4 3.14 Answer #3 may also be written to include MCC IH1-1 to sola transformers to vital bus 1-1 and cross-tied to VB 1-III.

4.03 Delete answer (6) from Answer Key - not applicable to Surry.

Add the following answers to Answer Key:

1) NIS dropped rod turbine runback annunciator

2) NIS dropped rod rod stop annunciator

3) IRPI dropped rod turbine runback annunciator

4) IRPI dropped rod rod stop annunciator ,

4.08(d) Answer should be start-up - a leak on the inner seal can be isolated.

Reference:

ND-88.1-LP-2, Page 11., Transparency 2.3.

Tech Spec 3.1-13.

4.10(2) The answer to this question is True due to the way the j question is written. The Administrative Procedure adds a

conditional statement but this does not affect the question asked in 4.10.

Reference:

SUADM-0-13, Page 10.

4.23 The answer for why steam pressure mode is used should be deleted and the following answer should be used in its

place

I iave mode is only used when Tave is 2 547*F. During a cooldown, Tave is ' 547 F so steam pressure mode must be used.

Reference:

hT-93.3-LP-9, Page 14,15,16.

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Mr. J. F. Munro Page 5 SENIOR REACTOR OPERATOR EXAMINATION QUESTION # COMMENTS 5.08 Comment the same as R0 question 1.04.

5.10 Comment the same as R0 question 1.08. l 5.12 No answer on Answer Key. Correct answer should be (a).

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Reference:

ND-86.2-LP-4, Page 4.11.

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! 5.16 Comment the same as R0 question 1.13.

5.18 Comment the same as R0 question 1.20.

5.20(a) Answer should be changed to DNBR

• 1.3; also add the follow-ing:

Reactor power less than 118% to prevent fuel pellet melting.

Reference:

Tech Spec 2.1-2 and 2.1-5.

6.05 Comment the same as R0 question 3.06.

6.09 Comment the same as RO question 2.23.

6.10(a) Answer should be (1) Loop A Cold Leg

Reference:

ND-88.1-LP-7, Transparency 7.7.

I 6.13 Comment the same as R0 question 3.10.

l 6.14 Comment the same as R0 question 3.11.

6.17 Comment the same as R0 question 2.22

6.19 Comment the same as R0 question 3.09.

7.11(d) Comment the same as R0 question 4.08.

I 7.12(2) Comment the same as R0 question 4.10.

7.13[A/.lZ.) Answer (a) should be 2 or 6 - both are NRC limits.

%R.o exg Answer (b) should be 2 or 4 - both are Station limits.

I 7.16 Answer (1) should be changed to: verify charging /SI pumps running instead of charging /SI flow.

Reference:

EP-1.00, Page 9, Step 20.

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Mr. J. F. Munro Page 6 j 7.24 Comment the same as R0 question 4.23.

8.07(b) Surry does not have a hot standby condition. This could

, lead to confusion by the candidates on time requirements for placing the plant in the required condition. This question should be deleted from the exam.

8.09 Add the following to the Answer Key:

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5) Number of victims

6) Estimated time of arrival at MCV

Reference:

EPIP-5.01, Page 3, Step 6.

8.17 Add the following to the Answer Key:

5) The status of any notification item has changed

6) Station Emergency Manager directions

Reference:

EPIP-2.01, Entry Conditions or Step 47,

7) Termination of event

Reference:

EPIP-2.01, Note Preceding Step 1.

Very truly yours, j Robert F. Saunders Arthur H. Friedman Station Manager Superintendent - Nuclear Training cc: Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station bc: Mr. W. L. Stewart Mr. J. L. Wilson l Mr. R. J. Hardwick Mr. G. L. Pannell Mr. D. A. Sommers Mr. H. L. Miller Mr. D. A. Benson Mr. D. A. Christian Dr. T. M. Williams i Training Department - Surry GOV 02 .54B NOD Tech. Library (bc original) l 4

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