ML20198Q774

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Forwards Rev 1 to Transient Analysis Lesson Plan, in Response to NRC 860414 Request for Addl Info to Complete Review of Proposed Licensing Candidate Training Program in Util
ML20198Q774
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/05/1986
From: Leonard J
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20198Q777 List:
References
SNRC-1261, NUDOCS 8606090364
Download: ML20198Q774 (4)


Text

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LONG ISLAND LIGHTING COM PANY

. 2uu~eaexcX SHOREHAM NUCLEAR POWER STATION P.O. DOX 618 NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 JOHN D. LEONARD.JR.

VICE PR ESiOENT. NUCLEAR OPE R ATIONS SNRC-1261 JUN O'51986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Additional Information License Candidate Training Program Shoreham Nuclear Power Station Docket No. 50-322

Reference:

Letter from Mr. W.R.

Butler (NRC) to Mr.

J.D.

Leonard (LILCO) dated April 14, 1986.

Dear Mr. Denton:

The above referenced letter requested additional information to enable your staff to complete its review of our proposed Licensing Candidate Training Program as presented in our letter SNRC-1230 dated January 31, 1986. of this letter contains your staff's requests for additional information and our response to each of these.

We anticipate that you will find these responses acceptable.

However, should you require further information or clarification regarding our reply, please do not hesitate to contact my office or members of my staff.

Very truly yours, hdQN' John D.

Leo' r Jr.

Vice Presiden

- Nuclear Operations TD/cf Attachment cc:

J. A.

Berry 8606090364 060605 0

0 PDR ADOCK 05000322 PDR g\\

ATTACHMENT 1 Page 1 of 3 Question 1.

The program identifies a Mitigating Core Damage and Accident Analysis training segment; however, there is no course description or outline.

Provide the course description or reference the program you have submitted in previous amendments to the FSAR.

Response

The following is an outline of the Mitigating Core Damage and Accident Analysis training segment of the program.as submitted via SNRC-1230.

This segment is presented during a one week time interval and contains the following ten lessons:

1.

Heat Source 2.

Gas Generation 3.

Core Cooling Mechanism 4.

Fuel and Core Damage Threshold 5.

Use of Fixed or Moveable Detectors 6.

Instrument Response During Accident Conditions 7.

Recognition of Inadequate Core Cooling Conditions 8.

Response of Process and' Area Radiation. Monitors 9.

Radiochemical Results From Degraded Core 10.

Degraded Core Corrosion Effects In addition to the above, a student handout entitled " Transient Analysis" is taught during this segment of the program.

A copy of the handout is attached as Attachment A.

Question 2.

Please identify the simulator that will be used in this program.

Response

The Limerick Simulator will be used for Shoreham's License Candidate Training Program as proposed in our previous submittal SNRC-1230 dated January 31, 1986.

Question 3.

With regard to drill scenarios conducted during simulator training, do the scenarios include manipulations and exercises contained in Item I.A.2.1 of NUREG-07377

Response

Yes.

Scenarios conducted during the simulator segment of the training program require candidates to react to simulated accidents in which the core is severely damaged.

Candidates are required to control or mitigate this accident based on information presented during classroom segments of the training program.

i

ATTACHMENT 1 Page 2 of 3 Question 4.

The 5 week (100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />) simulator training segment appears adequate to develop fundamental skills in conducting normal plant start-up and shutdowns.

In addition, the segment will include practice in abnormal and emergency procedures.

Addditional skills training in normal plant activities are continued in the following segments; however, there appears to be no continuing training in abnormal and emergency procedures.

Please identify continuing training in emergency orocedures; also include the setting which will be used for prpctice and evaluation.

Response

Continuing training in abnormal and emergency procedures will be accomplished during Qualification Guide walkthrough both in the control room and in the field.

In addition, classroom lectures will be utilized for continuing training in abnormal and emergency procedures.

Question 5.

The On-Shift Training segment does not require a minimum number of start-up, heat-up and shutdowns utilizing the Shoreham reactor.

We request a minimum of two start-ups (one for practice, the second for evaluation) for each license candidate.

Please note that the Shoreham reactor may be used to conduct operating tests.

Response

The Shoreham reactor will be used for training to the maximum extent practical when it is made available by operations personnel for training purposes.

Each candidate will perform two start-ups and heat-ups at the Limerick Simulator.

In addition, each student will pull ten criticals and perform a heat balance calculation at the Brook ~,aven Research Medical Reactor.

Question 6.

Outline the program or provide the objectives of the observation segment at an operating reactor.

Also include preparation before candidates begin observation training and the site (s) selected for observation training.

Response

The objectives of the Observation Training portion of the program are to provide the license candidate an opportunity to observe plant conditions at a steaming facility operating at or above 20%

power.

ATTACHMENT 1 Pago 3 of 3 It is expected that during the observation phase the license candidates will have an opportunity to observe the following:

o Reactor Power Manipulations o

Use of Process Computer Regarding Thermal Limits / Heat Balance to Interpret Data o

Complete Tech Spec / BOP Control Room Log Sheets o

Witness some of the following surveillance tests:

1.

Emergency Core Cooling System (ECCS) 2.

Reactor Core Isolation Cooling System (RCIC) 3.

MSIV Closure Test 4.

Main Turbine Control Valve, Stop Valve and Bypass Valve Testing 5.

Emergency Diesel Generator 6.

Standby Ventilation 7.

Neutron Monitoring Instrumentation 8.

Nuclear Steam Supply Shutoff System Testing Each license candidate will be trained on the Limmerick Simulator and/or have performed a portion of their Qualification Guide checkout during shift training prior to beginning the observation segment of the training program.

In addition, candidates will be required to bring a copy of the following material for reference during the observation segment of the program:

1.

Shoreham Technical Specifications 2.

SP12.016.03, Surveillance Program Checklist 3.

SP22.008.01, Operations Surveillance 4.

SP's 24 and 27, serves Tech Spec and non-Tech Spec Surveillance Procedures

~*

The following facilities will be used for Observation Training based on availability:

LaSalle Millstone Pilgrim I

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