ML20071K032
| ML20071K032 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/21/1982 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM TAC-44141, NUDOCS 8204270441 | |
| Download: ML20071K032 (9) | |
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P.O. Box 4 E
Shippingport, PA 15077 0004 h
April 21, 1982 8
'u Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Uashington, D.C. 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NUREC-0737; items I.A.2.1 and II.B.4:
Request for Additional In fo rma t ion.
Centlemen:
This letter has been written in response to your letter of March 16, 1982, Upgraded CR0 and RO Training and Training for Mitigating Core Damage - Request for Additional Information. The attached enclosure represents our response to each question coinciding with your request for information.
It should be noted that the information your review is based upon has undergone one revision and is presently undergoing a second.
Following approval, the latest revision of the Beaver Valley Power Station Training Manual will be Issue 3.
l If you have any questions, please contact my office.
Very truly yours, A
J. J. Carey Vice President, Nuc1 car Attachments 0
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4 Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Additional Information:
1.A.2.1 and II.B.4 Page 2 cc:
Dr. R. T. Liner Science Applications, Inc.
1710 Goodridge Drive McLean, Virginia 22102 Mr. D. A. Beckman, Resident Inspector U. S. Nuclear Regulatory Commission Beaver. Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Nbnagement Branch Washington, DC 20555
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DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit No. 1 Response to Request for Additional Information
!?! letter dated March 16, 1982 Question 1; The training programs for lic5nsed operating personnel consists of two options.
Under what conditions has Option I been exercised? Under what conditions has Option II been exercised? Are both options in effect now?
Response
Option I described the program developed at the Shippingport Atomic Power Station for use in training t'ne initial classes of personnel who were to license on the Beaver Valley Power Station, Unit No. 1.
When the Station organized its' train-ing section, Option II was developed as a new program for im-plementation by the training staff.
Option II is the current program in use and Option I has been retained in the Beaver Valley Training Manual (BVTM) for auditing purposes only.
In addition to the above programs and following the TMI in-cident, another section has been added to the BVTM to guide the licensing of those already certified to operate the Shippingport Atomic Power Station.
That section is attached as Appendix A and has been reviewed and accepted by the Operator Licensing Branch of the NRC (Refer to Paul Collins letter dated September 29, 1980).
Question 2:
The training programs for reactor operators (Option I and Option II) and the requalification program for reactor oper-ators (Section 2.2) include lectures which appear to have the potential for covering the subjects of heat transfer, fluid flow and thermodynamics as called out in Enclosure I of Denton's March 28, 1980, letter.
Do these lectures in fact cover these materials and is the coverage to the level spelled out in Enclosure 2 of the Denton letter?
Response
The training programs currently in use have been revised to include heat transfer, fluid flow and thermodynamics aed meet the requirements as identified by the NRC and additionally meet those requirements established by INPO.
Question 3:
The training program for licensed operating personnel Option I appears to contain no training in the area of accident miti-gation and training in dealing with transients as called out in Enclosure I of Denton's letter.
Does your training program Option I cover these areas and is the coverage to the level spelled out in Enclosure 3 of Denton's letter?
Response
Option I, as stated in response to Question 1, was the train-ing program used initially and has since been replaced with with Option II.
A training program entitled " Mitigating Core Damage" was developed to meet the NRC requirements and the Denton letter was used as a guide in the development of this program. This program is described in the BVTM Section 9.4 and is included as Appendix B to this letter.
Basvar Vallsy Powar Station, Unit No. 1
,, Razponse to R: quest for Additional Information NRC letter dated March 16, 1982 Page 2 Question 4:
The training program for licensed operating personnel Option II appears to have some potential for covering the training in the area of accident mitigation and train-ing in dealing with transients as called out in Enclosure I of Denton's letter. Does your training program Option 11 cover these areas and is the coverage to the level spelled out in Enclosure 3 of Denton's letter?
Response
The Option II training program satisfies these requirements through the inclusion of The Mitigating Core Damage Program as referenced in response to question 3.
Question 5:
Do the training programs for Options I and II each involve 80 contact hours under the subjects of heat transfer, fluid flow, thermodynamics and accident mitigation? Are there similarly 80 contact hours of heat transfer, fluid flow, ther-modynamics and accident mitigation in the requalification programs (Section 2.2)?
(A contact hour of instruction is a one-hour period in which the course instructor is present or available for instructing or assisting students:
- 1ectures, seminars, discussions, problem-solving sessions, and exam-inations are considered contact periods under this definition.)
Response
Option II provides the required training, but Option I does not.
The Mitigating Core Damage training is provided as a separate training course to those operators who have licensed under Option I.
The requalificatioa program includes 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> of training per year. The hours devoted to heat transfer, fluid flow, thermodynamics and accident mitigation vary depend-ing upon need but is normally less than 80 contact hours.
Question 6:
The reactor operator requalification program, Section 2.2.4.3, identifies nine reactor manipulations (Items (a) to (h) and (j)) along with ambiguous Item (1), plant and reactor opera-tion, that involve emergency or transient procedures where reactivity is changing.
Do these ten items cover all the twenty-seven manipulations identified in Enclosure 4 of the Denton letter?
Response
These manipulations represent those which may be performed in the station during normal operations. This section of the BVTM serves as a guide to licensed individuals as to what actual station manipulations may be performed which in-volve reactivity changes. This list is not intended to rep-resent all manipulations identified in the Denton letter.
The Denton letter states that "Those control manipulations which are not performed at the plant may be performed on a simulator." The requalification training program includes simulator training where all required manipulations are per-f o rmed. Our training program had included these prior to their formal establishment in the Denton letter.
Braver Valley Power Station, Unit No. I Respon:e to Request for Additional Information NRC letter dated March 16, 1982 Page 3 Question 7:
Are your instructors enrolled in appropriate requalifi-cation programs to assure they are cognizant of current operating history, problems, and changes to procedures and administrative limitations?
Response
Our present requalification program addresses each of these conceras.
Each licensed instructor attends the requalification program.
Item II.B.4; Request For Item II.B.4 provide an outline of the training program for mitigating core damage, including the number of training hours involved.
Your outline can include any training pro-gram which relates to the training for mitigating core damage.
Follow the guidelines given in the Enclosure 3 of H. R. Denton's letter dated March 28, 1980 and INPO Cuidelines for Training to Recognize and Mitigate the Consequences of Core Damage (Document Number STC-01, Rev. 1, January 15, 1981).
NRC re-quires a minimum of 80 contact hours of training for mitiga-ting core damage.
Response
Included with this submittal is Appendix B which provides the program description for Mitigating Core Damage.
Following in the number of training hours involved:
1.
Mitigating Core Damage Program 28 hrs.
2.
Simulator Training 40 hrs.
3.
Emergency Procedure Review, Incident Review - Module 1-4 8 - 20 hrs.
4.
Emergency Procedure Review - Module 5 24 hrs.
Total training directly associated with Accident Mitigation 100 - 112 hrs.
l Appendi,x A Pg. 1 DUQUESNE LIGHT COMPANY Beaver Valley Power Station Training Manual 2.6 SHIPPINGPORT OPERATOR CROSS-TRAINING,
2.6.1 Purpose To prepare certified Shippingport Atomic Power, Station operators for licensing at Beaver Valley Power Station.
2.6.2 Personnel to be Trained Shippingport Atomic Power Station operators who have'been certified more than one year.
2.6.3
- Scope of Training The Cross-Training program is approximately 18 bonths in length and includes academic training, systems qualification checks, simulator training, on-th-job f amiliarization and license review series.
2.6.4 Training Outline / Schedule 2.6.4.1 Academic Training Reactor Principles NET 3 80 Hrs.
Instrumentation and Operational Analysis NET 7 64 Hrs.
2.6.4.2 Systems / Watch Standing Cheeks Beaver Valley System Qual Checks 6 Mos.
On-Shift Familiarization 3 Mos,.
Simulator Training 1 - 4 Wks.
2.6.4.3 License Review Series (See Operation Training 16 Wks.
Section 2.3) 2.6.5 Administration of Program The Supervisor of Training is responsible for the overall administration of the Cross-Training program.
Personnel who are licensable, licensed or specifically knowledgeable in the field they are instructing vill be utili:ed to conduct the academic phase of training.
Systems qualification checks may be provided by qualified systems instructors.
Final systems qualification checks will be performed by licensed instructors.
2.26 ISSUI 3
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App:ndkxA Pg. 2 DUQUESNE LIGHT COMPA.VY Beaver Valley Power Station.
Training Manual t
License Review Series will be administered by licensed senior instructors.
Supervisor Skills instruction may be conducted by personnel recognized as knowledgeable in the specific field.
Simulator training will be conducted at a facility' approved by the NRC.
2.6.6 Records A record of qualification checks will be maintained for each i
student.
Results of all quizzes and exams will be maintained.
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2.6.7 Requirements and/or References JAW /JVV Letter #578, dated May 21, 1980.
Paul Collins' Letter, dated September 29, 1980.
.i 2.6.8 Summary of Figures and Forms None.
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DNQUESNE IIGHT COMPANY NPtndix B Pg. 1 B2evar Valley Powar Station Training Manual 9.4 MITIGATING CORE DAMAGE
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9.4.1 Purpose
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Thepurposeofthisprogra$t is to teach the use of installed equipment and systems to control or mitigate accidents in which the core-is severely damaged.
9.4.2 Personnel to be Trained 1
Shif t Technical Advisors and Operating personnel froa the Station Superintendent through ti e operatior.s chain, to the h
licensed operators shall receive all the training.
Supervisors and Technicians in RadCon, Chemistry, and I&C, shall receive training commensurate with their responsibilities.
9.4.3 Scope The program for mitigating core damage consists of six (6) four (4) hour lectures. (Lecture 1 is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in length.)
Each lecture is repeated six times.
I&C personnel will attend lectures 1, 2, 3, and 4.*
Chemistry personnel will attend Lecture. 1, 5 and 6.
Rad Con personnel will attend Lecture 1, 5 and 6.
9.4.4 Outline of Training The six (6) lectures are as follows:
Lecture I Core Cooling Mechanics / Gas, Steam Binding' Effects /Potentially Dama*ging Operating Conditions Lecture II Incore Instrumentation Lecture III Excore Nuclear Instrumentation Lecture IV Vital Instrumentation Lecture V Primary Chemistry Results with Core Damage Gas Generation Lecture VI Radiation Monitoring System 9.4.5 Administration of Program The Supervisor of Training is responsible for administering the program for Mitigating Cori Damage.
y,I Qualified Licensed instructors, edgineers, and health physics personnel may be utilized to preserf t 'the course.
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DUQUESNE LIGHT COMP JE Beaver Valley. Power' Station Training Manual 9.4.6 Records The Supervisor.of Training till maintain a record of all personnel receiving'the training.
9.4.7 Requirements and References
'NUREG-0737 II.B.4-1 NUREG-0660 II.B Letter from H. R. Denton to all power reactor applicants and licensees, dated March 28, 1980.
9.4.8 Summary of Figures and Forms.
Computer input roster.
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9.11 ISSUE 3
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