L-97-126, Submits Positions in Reference to Info Requested by R Croteau Concerning R Tetrick SRO License Exam Administered in June 1996

Submits Positions in Reference to Info Requested by R Croteau Concerning R Tetrick SRO License Exam Administered in June 1996

ML17354A502
Person / Time
Site:	Turkey Point
Issue date:	05/01/1997
From:	Hovey R FLORIDA POWER & LIGHT CO.
To:	Richards S NRC (Affiliation Not Assigned)
References
L-97-126, NUDOCS 9705150226
Download: ML17354A502 (9)

Text

CATZaoar j.

EI REGUl'ATORx INFORMATION DISTRIBUTION

~TEM (RIDS)

ACC'r'.SSION NBR:9705150226 DOC.DATE: 97/05/Ol NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C

05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION HOVEY,R.J.

Florida Power

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION RICHARDS,S.A.

SUBJECT:

Discusses positions of FPL re R Tetrick appeal of senior reactor operator license exam administered June 1996.

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M003D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Operator Requalification Program NOTES:

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1 RECIPIENT ID CODE/NAME CROTEAU,R NRR/DRCH/HHFB RGN2 NRC PDR COPIES LTTR ENCL 1

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MAY 1 t997 L-97-126 Stuart A. Richards

'hief, Operator Licensing Branch, NRR U.

S. Nuclear Regulatory Commission White Flint North 11555 Rockville Pike Rockville, Maryland 20852

Dear Mr. Richards:

Re:

In reference to information requested by Mr. R. Croteau related to Ralph Tetrick's NRC Senior Reactor Operator (SRO)

License Exam administered June 1996, Florida Power

& Light Company (FPL) has the following positions:

A personal letter was sent by our employee Mr. Brian Stamp representing his personal opinion about Question 063 of the NRC SRO Exam.

Since this was a personal letter, not on a company letterhead nor signed by an officer of the

company, it does not represent the position of FPL.

2.

If the question is interpreted to be asking for an Off Normal Operating Procedure (ONOP) immediate action, response (b) is correct.

Question 063 however, asks for an IMMEDIATE ACTION without specifying that it is looking for the ONOP IMMEDIATE ACTION.

The only way this is implied in the question is by the words "IMMEDIATEACTION" being capitalized, which is the format used in the ONOPs.

l

)

If the question is interpreted to be asking for an immediate action for the receipt of an annunciator, response (a) is QQ75 correct.

Management's policy and expectation of operators is to validate all alarms by checking appropriate instrumentation prior to taking action.

Additionally, the Annunciator Response Procedure (ARP) instructs the operator to verify the alarm with the indications contained in response (a).

See the attached ARPs for the two annunciators listed in Question 063.

It is FPL's position that the best answer to the question is response (b), but that the question could be interpreted such that response (a) is also correct.

As a result, Question 063 as written, has two possible correct answers.

9705 f50226 r97050i PDR ADOCK 05000250 PDR

'lllNlljllIllllllllllllllltlml an'FPL Group company

L-97-126 Page 2

3.

Management's policy and expectation of operators to validate all alarms by checking appropriate instrumentation prior to taking action has been reinforced in the simulator training program.

This policy provides assurance that the appropriate actions are being taken for valid plant conditions and does not result in an operator failing to follow an appropriate procedure.

Very truly yours, R. J.

Hove Vice President Turkey Point Plant OIH cc:

T. A. Peebles, Chief, Operations

Branch, Region II, USNRC L. A. Reyes, Regional Administrator, Region II, USNRC Document Control Desk, USNRC T. P.

Johnson, Senior Resident Inspector,

USNRC, Turkey Point Plant

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procedure No.:

3-ARP-097.C R Proc e Titie:

Control Room Annunciator Response age: 393 Approval Oate:

6/10/93 1

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BLUE H1 INVESTMENTPROTECTION ATTACHMENT8 Page 1 of54 Panel H H 1/1 SFP LO LEVEL 123456789 DEVICES:

Level actuator at nort'h end ofSFP SETPOINTS:

56'0" LT-3-651 OPERAT'OR ACTIOiTS.

il ", Vecrify al raem'Tty'Ihclecki ng thefollorvingg

~-a".'. L'I-'3-:631'(VPB)'i'g~

2.

Corrective actions:

a.

Dispatch operator to check:

(1) Spent fuel level indication I Y-3-651 (behind VPB)

(2) Local level at the SFP.

(3) Power to LT-3-651 (LP-50, Bkr 19 - east wall ofcable spreading room.

b.

Refer to 3-0NOP-033.1, SPENT FUEL PIT (SFP) COOLING.

c.

IF in a refueling configuration with the SFP transfer tube open, THEN terminate refueling operations and refer to 3-ONOP-033.2, Refueling avity Seal Failure System Malfunction for cavity seal failure required actions.

d.

Refer to TS 3.9 for additional actions.

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lfSFP cooling has to be secured, monitor SFP temperature per Attachment 3 of 3-OP-033, notifyReactor Engineering.

Ifannunciatoris OOS, refer to O-ADM-2l4.

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e m o m e ~ o m e m e m e I CAUSES:

l.

Actual low level in SFP (Evaporation, leakage, or SFP system valve misalignment) 2.

Loss ofpower to LT-3-651 3.

Instrumentation failure

REFERENCES:

1.

FPL DWG 5613-M-3033 Sh 1 2.

Tech. Spec. Section 3.9 a 'e ji.C OC =C OSC

Procedure No.:

3-ARP-097.'CR r

e Title P

Control Room Annunciator Response 391 Approval Date 8/6/92 1

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6 BLUE G45 INVESTMENTPROTECTION ATI'ACHMENT7 Page 53 of54 Panel G G 9/5 CNTMT SUMP HILEVEL 1 23 4

546 78 9

DEVICES:

R-1418 (unit 4 VPA)

SETPOINTS:

30il (OPERATO> A.CASIONS:

'1.

P ilP I

pp'8 pljjp lll ':

DNPNP 8

d 1418 j 4 PP8),

8-481188lp, d DDPP p I DDPSA'102=3.

2.

Corrective actions; a.

Verifyproper operation ofthe containment sump pumps.

b.

Pump down the sump as required.

c.

MonitorRCS parameters for indications ofleak, ifapplicable.

d.

Perform 3-0SP-041.1 to determine the RCS leak rate, ifapplicable.

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I 'fannunciatoris OOS, refer to O-ADM-214.

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l CAUSES:

1.

RCS leak.

2.

Instrument malfunction.

REFERENCES:

1.

FPL DWG 5610-M-12

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