ML20132C935

Exam Rept 50-348/OL-85-02 on 850805-08.Exam Results:Eight Candidates Passed & Eight Failed

ML20132C935
Person / Time
Site:	Farley
Issue date:	09/12/1985
From:	Douglas W, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20132C923	List: ML20132C921 ML20132C935
References
50-348-OL-85-02, 50-348-OL-85-2, NUDOCS 8509270189
Download: ML20132C935 (6)

Text

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ENCLOSURE 1 EXAMINATION REPORT 348/0L-85-02 Facility Licensee: Alabama Power Company 600 North 18th St.

Birmingham, AL 35291 Facility Name: Farley Nuclear Plant Facility Docket No.: 50-348 Written, simulator and oral examinations were administered at Farley near Ashford, Alabama.

Chief Examiner: Ld Mm. M .9 William G. Douglas 9 415/85

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Date Signed Approved by: AM O- , A Brupe A. Wilson, Section Chief I W Dhte S'igned Summary:

Examinations on August 5 - 8, 1985 Written, oral.and simulator examinations were administered to ten RO candidates; six of whom passed all three examinations.

Written, oral and simulator _ examinations were administered to three SR0 candidates; one of whom passed all.three examinations.

Oral and simulator examinations were administered to one.SRO candidate who passed both examinations.

Simulator retakes were administered to two SRO candidates; neither of whom passed the simulator examination.

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REPORT DETAILS

1. Facility Employees Contacted:

• J. D. Woodard, Plant Manager

• W. B.. Shipman, Asst. Plant Manager

• R. D.-Hill, Operations Superintendent

• L. S. Williams, Site Training Director

'*R.. Wiggins, Training Supervisor

• R. Vanderbye, Instructor

• C. McLean, Instructor

• B. Bradford, NRC Senior Resident Inspector

• Attended Exit Meeting

2. Examiners:

• W. G. Douglas, NRC W. M. Dean, NRC P. V. Doyle, NRC W. Hemming, EG&G R. Picker, EG&G

• Chief Examiner

3. Examination Review Meeting Prior to the Exit Meeting, the examiners met with Lee Williams and Randy Wiggins to review the written examination and answer key. The following comments were made by the facility reviewers:

a. SRO Exam (1) Question 5.12 Facility Comment:

The possible answers relate subcooling margin to Tavg vice Thot; therefore, no correct answer exists.

NRC Resolution:

-Agree with comment. Question deleted.

(2) Question 6.08 Facility Comment:

Possible' answers contain two correct responses to the design basis of containment spray.

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Enclosure 1 2 NRC Resolution:

Two separate segments in the same facility training document disagree on whether preventing containment design . pressure from being exceeded after a LOCA is a design basis or not. Will accept answers "a" or "b" for.this question, but facility should correct this discrepancy between page 1 and page 6 of FNP-SD, "Contain-ment Spray".

(3) Question 6.19 Facility Comment:

Correct answer should be "d" vice "c".

NRC Resolution:

Agree. Answer key will be so modified, as verified by page 19 of FNP-SD, "EDG Sequencers".

(4) Question 6.20(c)

Facility Comment:

Correct answer should be " ARM only" vice " Arm and actuate" NRC Resolution:

Agree. Answer key to be so modified. Verified in FNP-SD, " Steam Dump System" pp 23-28.

(5) Question 6.27 Facility Comment:

Question asks for in-depth knowledge of interlocks associated with a breaker which-is rarely used and whose operation is expressly covered in its operating procedure. Question ~ should be deleted.

NRC Resolution:

Breaker operation was expressly dealt with in facility training material, ~but in light of the highly-infrequent operation and the minor loads associated with this breaker, question is deleted.

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'(6) Question 7.05 Facility Comment: -

Question requires . candidate to memorize the ordering of some unrelated subsequent actions in an emergency procedure and should be deleted, or several possible answers allowed.

NRC Resolution:

Agree with facility comment in that some of the actions in .he procedure would not logically occur before/after other listed actions. Question deleted.

(7) .Qu.estion 7.17 Facility Comment:

Question asks candidate to reproduce a critical safety function curve whose parameters are usually interpreted by the SR0 in an accident con'dition, but not committed to memory.

NRC Resolution:

Although the function of the curve and 'its importance to reactor safety are . vital' knowledge, agree with facility comment that committing specific parameters and curve regions to memory is not

-appropriate for senior ope'rators. Question deleted.

(8) Question 8.18(a)

Facility Comment:

Answer key should read "True" vice " False".

NRC Resolution:

Agree. Answer key so modified. Verified 'in'TS pp. 3/4.0-1/2.

(9)- Question 8.23(b).

Facility Comment:

Determining 'the answer requires memorization of a T/S table.

NRC Resolution:

' T/S 3.4.7.2 contains ,a full page table ' for RCS ' leakage limits . for

' specific valves'and ,should not be committed to memory. Quistion deleted.

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Enclosure 1 4 (10) Question 8.30 Facility Comment:

.The ' P-12 basis listed -in Technical Specifications for Minimum Temperature for Criticality does not apply to Farley as their P-12 setpoint is 2 above the MTC.

NRC Resolution:

Agree. Answer key modified to delete this as a required part of the answer; even though their generic Tech Spec's list this as a basis for the MTC limit, verified P-12 setpoint in FNP SD, "Tavg, Pimp and Delta T".

b. R0 Exam

.(1) Question 1.1 - See SRO 5.12

.(2) Question 2.07 - See SR0 6.08 (3) Question 2.10 - See SRO 6.19 (4) Question 3.03 Facility Comment:

P-10 is not an " interlock" for the Source Range Trip and should .

not be required as an answer.

NRC Resolution:

Agree. Answer key so modified.

(5) Question 3.10 Facility Comment:

ho answer is lis,ted-in the answer key.

NRC Resolution:

The correct answer was inadvertently omitted and will be inserted

-as stated in FNP-SD " Diesel Generators" pp 28/29.

(6) Question 3.23(c) - See SR0 6.20(c)

(7) Question 4.11 - See-SRO 7.05

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(8). Question 4.16(b) - See SR0 8'.23(b) wa: -

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Enclosure 1 '5

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. Those individuals who clearly passed the oral examination were identified.

The NRC examiners' expressed concern over the facility's continued poor performance on simulator exams and -the facility demonstrated a high degree of interestiin alleviating this situation and obtaining any insights into what they can do to help their candidates improve.

The examiners noted inconsistent use of Abnormal Operating Procedures (AOPs) among the candidates and stressed that use of A0Ps is important in correctly analyzing and recovering from' abnormal' conditions.

The cooperation ~given to the examiners and the effort to _ ensure an atmosphere 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.

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