ML19289F272

Responds to NRC Questions in 790523 Meeting Re Analysis of Diesel Generator Pickup,Emergency Feedwater Flow Indication, Autostart Annunciation in Control Room & Permanent Operator Training Staff.Two Oversized Drawings Encl

ML19289F272
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/24/1979
From:	Trimble D ARKANSAS POWER & LIGHT CO.
To:	Reid R Office of Nuclear Reactor Regulation
References
1-059-34, 1-59-34, NUDOCS 7906070138
Download: ML19289F272 (7)

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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. APKANSAS 72203 (501) 371-4000 May 24, 1979 l-059- 34 Director of fluclear Reactor Regulation ATTN: Mr. Robert W. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Response to Verbal Questions fran May 23, 1979 Meeting (File: 1510)

Gen tlenen:

The following is provided in response to concerns of the staff raised in the I:ay 23, 1979 meeting at Arkansas Nuclear One - Unit 1 (ANO-1).

Item 1 Can the diesel generator pickup the Al (EF' pump) bus load? (Where is the analysis?)

Re s po nse An analysis was conducted to de'armine if the 700 hp motor driven Emergency Feedwater Pump could ;e loaded on the emergency diesel gen-e ra to r. This analysis was prc,ided to the NRC in our December 3,1973 letter to Mr. A. Giabusso and concluded that the diesel generator could accept the load.

Item 2 Demonstrate the perfonnance of the new EFW flow indication and autostart annunciation in the control room. Denonstrate the nininum acceptable flow (550 GPM) fran each EFW train.

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Mr . R. W. Re id May 24,1979 Demonstrate the new autostart feature on the electric EFW pump actually works. Demonstrate the capability of the manual control of the EFW system to maintain S.G. level with the EFW bypass valve.

Respons e As discussed in our May 21,197o letter, we propose to demonstrate: (1) perfomance of the EFW flow indication and auto start annunciation modi-fications, (2) minimum acceptable flow (i.e. 550 GPM) capabilities of each train of EFW, (3) operability of the auto start modification on the motor driven EFW pump, and (4) capability of manual control of steam generator level with the EFW bypass valve. This test will be perfomed prior to exceeding 15% of rated power and in accordance with Test Pro-cedure No. 79, Flow Test Emergency Feedwater to the Steam Generators with Manual ICS Override, subject to approval by your staff.

Item 3 The NRC requires that 16 core exit themocouples, recorded in the vi-cinity of the penetration, be provided as a condition of startup. Also, timely (1-2 weeks) relocation to the control roan is required.

Response

.To satisfy a recent concern of the staff, sixteen (16) incore themo-couples will be connected and have recording capability before we begin power operathn as defined by Technical Specification 1.2.5 (i.e., above 2 percent of rated power). These themocouples will be connected so as to provide input to the plant computer for readout purposes as soon as practicable following startup. An additional sixteen (16) incore thermo-couples will be ;onnected so as to provide ' inputs to the plant computer by October 31, 1979.

Item 4 Provide a procedures guideline or flowsheet to help lead the operator to the correct procedure.

Response

Prior to startup, a procedures guideline ar flowsheet will be available in the control roon to guide operator in detemining which procedure to use given a set of circums onces. Your I&E inspector will verify this action to have been taken.

Item 5 Has the reactor trip setpoint been set at 2300 psig and the PORV relief set at 2450 psig?

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Mr. R. W. Reid tiay 24,1979

Response

Our letter of April 24, 1979, proposed changee so the Ati0-1 Technical Specifications. Specifically, our request involved raising the PORV opening setpoint fraa 2255 psig to 2450 psig and lowering the high pres-sure ret tor trip setpoint from 2355 psig to 2300 psig. These setpoint changes have been made and the revised setpoints will be utilized admin-istratively until an amendment to the Technical Specifications is issued.

Item 6 Commit to a schedule, and the exclusion from duties as R0/SRO, for re-training those operators who did not pass the written exam or else who showed deficiencies during the tiRC audit.

Response

The licensed operators who did not pass the written examination and the licensed operators who showed deficiencies during the flRC audit will be excluded fran duties as Reactor Operator or Senior Reactor Operator prior to power operation and until such time as they have received additional training and have passed a written examination. This additional training and examination shall be completed by June 1,1979.

Item 7 If an operator fails the initial exam, no additional exam shall be taken until retraining has been done. Also, the second exam must be different from the first.

Res ponse If a licensed operator failed the initial written examination, additional training will be conducted prior to administering a second examination.

The second written examination shall be different than the initial writ-ten examination. If a licensed operator fails the second written exami-nation, an individualized training program will be devu.'oed for that individual. This training program shall be reviewed and approved by the NRC. A third examination will not be given to the individuul until the individualized training program is completed.

Item 8 Describe the pennanent ANO operator training staff.

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Mr. R. W. Reid May 24,1979

Response

Although the plant is authorized to have a training staff of six people, only three positions are currently filled. The organization is as foi lows :

POSITION ASSIGNED INDIVIDUAL Training and Counseling Supervisor Mr. Jimmy Vandergriff Training Coordinator (Unit 1 ~0perations Mr. Tracey Green Training)

Training Coordinator (Unit 2 Operations Training) Open Training Coordinator (Electrical Skills Training & Mechanical Skills Training) Mr. Bruce Baker Training Coordinator (I&E/ Technical Support Training) Open Training Coordinator (Supervisory / Career Pa th Planning) Open Backaround Summary for AND Trainino Staff Jimmy Vandergriff - Training and Counseling Supervisor 8 years of Navy nuclear power experience including 3 years as ET on nuclear submarine and 3 years as instructor at AlW prototype. 9 years at ANO in-cluding 1) 2 years as a ;hift supervisor on Unit 1, 2) 2 years as a shift supervisor on Unit 2.

Licensed as SRO on Unit 1 and Unit 2 (cold license on both).

Tracey Green - Training Coordinator - Operations 2h years of fossil plant experience in operations, maintenance, I&C, and plant performance 2 years of experience in AP&L Production Dept.

6 years in plant testing, perfonaance and analysis.

6 years of experience in training at ANO including operator training and general enployee training.

Holds BS degree in Math.

Bruce Baker - Training Coordinator Maintenance 2 years as Test Engineer with Aberdeen Proving Grounds.

10 years in R&D engineering with Dow Chemical in Chlor-Alki production.

4 years as Assistant Maintenance Supervisor at ANO.

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Mr. R. W. Reid May 24, '

1 years as Maintenance Training Coordina a t ANO.

Holds BSME frm University of Arkansas (if It is intended the open positions be filled with mople of the following qualifications:

Training Coordinator - Ooerations Unit 2 Requires BS in Engineering or Physical Sciences or the equivalent frm iob experience and techni-cal training.

Minimum of 4 years of work experience in power plant related field.

Operator license desirable.

Training Coordinator - I&C and Tech Support Same as Training Cordinator above.

Career Counseling and Supervisor Training Coordinator Requires a degree in management, engineering, or a field in which management and counseling / psychology skills training are included. Also 2 years technical /

supervisory experience or 5 years experience in technical supervisory position.

Currently, Mr. Vandergriff conducts the major portions of the Unit 2 operations training until the Unit 2 training position is filled.

Based on discussions with your staff, we believe the itens necessary for issuance of a release fran our May 17, 1979 Order have been completed or addressed to the satisfaction of the staff. Therefore, we request the issuance of said release on May 25, 1979.

Also, attached are additional copies of schematics provided previously, These show the modification to provide.an autostart of EFW upon loss of main feedwater and the annunication of this autostart.

Very truly yours, bGLY (- h David C. Trimble Manager, Licensing DCT/DGM/ew Attachments 2232 7.