ML20214A244

Exam Rept 50-250/OL-86-04 on 860908-11.Exam Results:One of Four Reactor Operator Candidates & Three of Four Senior Reactor Operator Candidates Passed Oral &/Or Written Exams

ML20214A244
Person / Time
Site:	Turkey Point
Issue date:	10/21/1986
From:	Bill Dean, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
References
50-250-OL-86-04, 50-250-OL-86-4, NUDOCS 8611190332
Download: ML20214A244 (6)

Text

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ENCLOSURE 1 EXAMINATION REPORT 250/0L-86-04 Facility Licensee: Florida Power and Light Co.

P. O. Box 14000 Juno Beach, FL 33408 Facility Name: Turkey Point Units 3 and 4 Facility Docket No.: 50-250 and 50-251 Written and oral examinations were administe ed at Turkey Point Nuclear Plant near Florida City, Florida f j Chief Examiner: / d(K /

._ d ,2 / o c F d3 William M. Dean Date Signed Approved by: # d " C 6cd N Jogn F. Munro? ActMg Section Chief Date Signed Summary:

Examinations on September 8-11, 1986 Oral examinations were administered to 5 candidates; 3 of whom passed. 5 candidates were administered written re-examinations; 3 candidates passed.

Based on the results described above,1 of 4 R0's passed and 3 of 4 SR0's passed.

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8611190332 861021 PDR ADOCK 05000250 V PDR

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REPORT DETAILS

1. Facility Employees Contacted:

• J. Kappas, Acting Plant Manager

• W. Miller, Training Supervisor Nuclear

• T. Finn, Asst. Operations Superintendent

• P. Baum, Operations Training Supervisor

• G. Hollinger, Training Staff

• Attended Exit Meeting

2. Examiners:

• William Dean Chuck Casto Lawrence Lawyer

• Chief Examiner

3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided your training staff with a copy of the written examination and answer key for review. The comments made by the facility reviewers are included as Enclosure 3 to this report, and the NRC Resolutions to these comments are listed below.

a. R0 Written Exam Resolutions (SRO questions in parentheses)

(1) Question 1.03 (5.01) Do not concur. The traces provided in this question are based upon a generic PWR transient and without NRC analysis of the events which were simulated at Westinghouse, no conclusions can be formulated. However, based upon Turkey Point's Tcold program a possibility exists that iuold may increase slightly depending upon the steam dump pressure setpoint. Because the steam pressure setpoint was not provided in the question, this question is deleted.

(2) Question 1.10 (5.07) Agree with facility comment that steam dunps to the condenser would not be operational, however, this has no impact on the ability of the question to clearly axpress its purpose. Agree that increasing the steaming rate will increase the driving head, but the question states that S/G pressure and levels are maintained stable which implies little variation in steaming / feeding rates. Finally, the referenced theory text expressly states that as corrective flow increases, a resultant decrease in fuel element temperature (implying below the initial rise causing the higher core exit temperature) will occur, i.e., a

" corrective" decrease. Question and answer key stand as is.

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2 (3) 1.12 (5.09) Concur. The responses to this question will be graded in accordance with the facility reference material provided. Any equivalent answer will be evaluated on a case-by-case basis for their adequacy. No change to answer key required.

(4) 1.13(a) (5.10(a)) Agree that maximum operating loop temperature is not the same as Tavg, but question clearly references the appli-cable curve to be considered in answering the question. Under-standing how the safety limit curves are generated is considered appropriate for reactor operator candidates. It is a Technical Specification related topic important to plant operation. NUREG 1021 recommends the use of NUREG 1121 as guidance in selection of written examination questions and KA PWG-5 for system 002/020 (RCS) lists the importance factors for this topic as 2.9 for R0s and 4.1 for SR0s, both well within guidelines for appropriateness of the topic. No change to question or answer key.

(5) 1.13(c) (5.10(c)) Curve c of supplied drawing is referred to in the documented reference as being applicable to the construction of the higher pressure safety limit curves. As this text was used in Turkey Point Operator Training and no documentation exists to support non-applicability of this curve, question will not be deleted. However, the facility's recommended answer (which is a restating of the existing answer) will be an acceptable reply.

(6) 1.14(c) (5.11(c)) Concur. Any three of the four signals will be an acceptable answer. Answer key revised to add High Steamline flow with low Tave or low S/G pressure. Reference used by NRC needs to be modified to reflect correct information.

(7) 1.16 (5.13) Concur. Due to the reference made in the question to redistribution, the answer key is revised to accept answers which accurately explain redistribution, as it applies to BOL power changes, in accordance with facility reference material. In addition, the accurate explanation of two of the three reasons will suffice for full credit. Answer key modified.

(8) 1.19 (5.16) concur. The question is based upon a theoretical core and did not refer to either Turkey Point unit in particular.

However, it is acceptable to include the effects of Cycle X. In addition, answers which describe two bases for flattening of the flux in the middle of the core are acceptable for full credit due to wording of question possibly leading examinees to this answer.

(9) 1.21(a) (5.18(a)) Do not concur. Westinghouse Background documents specifically refer to the active (core + loop) portion of the RCS. This was also highlighted in the question. No change to answer key.

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3 (10) 2.03 (6.02) Concur. Recent change to procedures not held by NRC, modified the HOT LEG Recirculation lineup. Answer key changed to "b".

(11) 2.11 Concur. System modifications not reflected in facility provided material held by NRC and should be corrected. Answer key changed.

(12) 2.12(a) (6.13(a)) Concur. Inconsistencies in facility reference material provided for this examination may have led to incomplete answers by the candidates. Answers which state "CS to start" or

" Breaker closed and CS to start" will be considered equivalent answers. Suggest facility correct reference material.

(13) 2.13(a) Concur. Answer key will be modified to accept indication as another use of the cts for full credit based on new material provided to the NRC.

(14) 2.13(b) Concur. Answer key modified to require Alarm in control room as part of the answer, as well as suitable ground detection methods.

(15) 2.16 Do not concur. Referenced System Description expressly states that a natural circulation process exists to maintain seal water flow. Without documentation to support facility's recom-mended answer, no change to the key can be made.

(16) 2.19(a) (6.17(a)) Do not concur. This fact was clarified by the proctor to all examinees during the exam. No change to answer key required.

(17) 2.19(c) Do not concur. Question's basis was to determine if the

examinee knew what, if any, effects the control circuit for the

! Trip & Throttle valve has on system operations. No change to answer key required.

(18) 2.19(e) Concur. Facility reference material depicts the main oil i

pump supplying the governor. The examiner has determined by local I

observation that this is not the correct flow path. Therefore, I answer key changed to accept "will inject" with an accompanying

( explanation of the effects of loss of lubrication. Suggest

facility correct reference material.

(19) 2.22 Concur. Will accept any correct design flow balance, based i

on orifice selected, and the value of CCW flow through the thrust >

j bearing.

! (20) 3.08(d) Concur. Answer key changed to reflect change in facility l design, not reflected in material held by NRC.

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(21) 3.09(a) Concur. An error was made in answer key development.

(22) 3.14(a) (6.20(a)) Concur. Setpoint not elicited by question.

Answer key modified.

(23) 3.15(a&b) (6.21(a&b)) Concur. Recommended answers are equivalent to answer key. No change to answer key required.

(24) 3.16(b) Do not concur. Question asked for the " exact" effect of FC478 on the valve. This directly implies a description of the controls was required for full credit. No change to answer key required.

(25) 3.18(b) (6.22(b)) Concur. Question asked for actions, not a description of a transient. Answer key changed.

(26) 3.18(c) Concur. Answer key changed to add trips. Facility should correct existing re#erence material.

(27) 3.19(b) Concur. Question did not clearly identify bistable trip only, therefore, ccrrect additional responses to power range detector voltage loss will be accepted.

(28) 4.04 (7.04) Concur. E0P-E-0 note 1 does direct use of CSF status trees via the foldout page. Answer key changed to accept both answers.

(29) 4.16 (7.15) Concur. Question deleted since it did not clearly distinguish between integrated and system specific OP's.

(30) 4.19 (7.23) Concur. Answer key changed to include recommended additional answer. Referenced facility material should be corrected.

(31) 4.20 (7.21) Concur. Due to procedure change since exam reference material was supplied, only one step in ONOP-28 is required.

Answer key changed to reflect this.

(32) 4.24 (7.25) Concur in part. Correct discussions on the target l

I band limit will be acceptable as +0.75 points, as it is discussed l in the referenced procedure, but coincidence of NI's is required to gain full credit,

b. SRO Exam Comments (1) Question 7.19 Do not concur. Facility supplied reference for comment is based upon an E0P which does not apply to the given situation. The question is based upon responses contained within l an ONOP. Answer key changed to reflect +0.5 credit for " Initiate I containment vent isolation."

5 (2) Question 8.22 Concur. Part a changed to accept "4" as a correct response due to SI pump requirements also contained in TS. Note that this requirement conflicts with requirements of TS referenced in answer key.

c. Post-examination review resulted in the following changes.

(1) 1.18(5.15) Answer key essentially had redundant answers. Key modified to require only the first two responses (or similar answers).

(2) 4.09(b)(7.08(b)) Due to incorrect information in facility E0P foldout page with regards to S/G level, changed answer key to "No" (not CSF Red Path). Facility needs to correct contradictory information in their E0Ps.

(3) 4.18(7.17) Due to change in operating procedures, not reflected in material sent to the NRC, question is deleted, as it no longer applies.

4. Exit Meeting At the conclusion of the site visit the examiners met with representatives 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 atmos-phere in the control room conducive to oral examinations was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners, l

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