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Goerp Powst Company | |||
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* t 3M P Wont Aseoue Myn, Gwq,a 30Y)3 bepoore 404 526 6526 UWg Arcsi PvA Ctf.ce Sex 4545 Ms ta. Gectg a 3%02 R. P. Mcdonald tre soutNvn ewinc systern E>ecutwe V ce Pres de-t PL Jear Cwatmc SL-4744 0956m X7G;17-V600 June 14, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIF1f.ATION 6.3 - TRAINING Gentlemen: | |||
In accordance with 10 CFR 5').90 as required by 10 CFR 50.59(c)(1), | |||
Georgia Power Company (GPC) hereby proposes to amend the Vogtle Electric Generating Plant Unit 1 Technical Specifications, Appendix A to Operating License NPF-68. . | |||
The proposed amendment incorporates recent changes to 10 CFR 55 into the licensing program. | |||
Enclosure 1 provides a detailed description of the proposed changes and the bases for the changes. | |||
l Enclosure 2 details the basis for our determination that the proposed changes do not involve significant hazards considerations. | |||
I Enclosure 3 provides instructions for incorporating the proposed changes into the Technical Specifications. The proposed correct page follows Enclosure 3. | |||
In accordance with 10 CFR 170.12, a check for payment of the $150.00 license amendment filing fee is enclosed. | |||
' l | |||
' $lA Wi g, "8806240073 880614 PDR P | |||
ADOCK 05000424 DCD b | |||
[ | |||
t Georgia Power d U. S. Nuclear Regulatory Commission June 14, 1988 Page Two Mr. R. F. Mcdonald states that he is Executive Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true. | |||
GEORGIA POWER COMPANY l | |||
By: . N1 R. P. Mcdonald Sworn to and subscribed before me this 14th day of June,1988. | |||
/ [1 Notary Public ner ND$ | |||
PAH/im | |||
==Enclosures:== | |||
: 1. Basis for Proposed Changes | |||
: 2. 10 CFR 50.92 Evaluation | |||
: 3. Instructions for Incorporation | |||
: 4. Check No. 044779 for $150.00 filing fee c: Georaia Power Comoany Mr. P. D. Rice | |||
! Mr. G. Bockhold, Jr. | |||
GO-NORMS U. S. Nuclear Regulatory Commission i Dr. J. N. Grace, Regional Administrator i Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies) I Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle 0956m l | |||
l | |||
Georgia Power d ENCLOSURE 1 PLANT V0GTLE - UNIT 1 NRC COCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 BASIS FOR PROPOSED CHANGES PROPOSED CHANGE Revise Paragraph 6.3.1 to read as follows: | |||
6.3 Trainina 6.3.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Plant Training and Emergency Preparedness Manager. Personnel will meet the minimum education and experience recommendations of ANSI N18.1-1971 and, for licensed staff,10 CFR 55.59 and the supplemental requirement specified in Sections A and C of Enclosure 1 of the . March 28, 1980 NRC lette' to all licensees, before they are considered qualified to perform all duties independently. Prior to meeting the recommendation of ANSI N18.1-1971, personnel may be trained to perform specific tasks and will be qualified to perform those tasks independently. Personnel who complete an accredited program which has been endorsed by the NRC shall meet the requirements of the accredited program in lieu of the above. | |||
BA_SLS In Generic Letter 87-07, it was stated that the 55.59(c) content requirements (formerly Appendix A to 10 CFR 55) can be met with a performance-based program for a facility as approved by the NRC. In its : | |||
Final Policy Statement on Training and Qualification of Nuclear Power l Plant Personnel, the Commission endorsed industry-accredited programs as ! | |||
performance based. l In the Federal Register Volume 52 No. 57 dated Wednesday, March 25, 1987, it was stated that: | |||
"The requalification program must meet the requirements of paragraphs (c)(1) through (7) of this section. In lieu of paragraphs (c)(2), (3), | |||
and (4) of this section, the Commission may approve a program developed by using a systems approach to training." | |||
0956m El-1 06/14/88 SL-4744 i | |||
Georgia Power d i | |||
ENCLOSURE 1 (Continued) | |||
REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 BASIS FOR PROPOSED CHANGES The proposed change to the training sections reflects the sentiments of the Commission by allowing the use of a performance based industry-accredited program for training of the licensed staff. | |||
0956m El-2 06/14/88 SL-4744 | |||
Georgia Power d ENCLOSURE 2 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 10 CFR 50 92 EVALUATION In accordance with 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment to the VEGP Unit 1 Technical Specifications and has determined that operation of the facility in accordance with the proposed amendment would not involve significant hazards considerations. | |||
BACKGROUND The purpose of this technical specification change is to mirror the changes in requalification program requirements that recently appeared in the Code of Federal Regulations, Vol. 52 No. 57, Wednesday, March 25, 1987. The code now allows the Commission to approve a program developed by using a systems approach to training. | |||
: 1. The proposed change does not significantly increase the probability or consequences of an accident previously evaluated. This change allows recognition # a training program that has received an NRC endorsement or approval. Since the plant operating staff will be "approved", the probability of any previously evaluated accident is not affected. The consequences of previously analyzed accidents are r.ot significantly increased. | |||
: 2. The proposed change does not create the possibility of a new or different kind of accident than any accident previously evaluated. | |||
The plant operating staff is still subject to an NRC approved program. A new or different failure mode should not result from the training given to the operating staff. | |||
: 3. The proposed change does not involve a significant reduction in the margin of safety. Plant operations perunnel, both before and af ter the change, operated the plant subject to NRC review and approval of their training. In this case, the NRC is approving or endorsing a performance based training program. Safety margins are therefore not reduced since the operation . raining program is still subject to NRC 7 | |||
review and approval. | |||
0956m E2-1 06/14/88 SL-4744 | |||
Georgia Power d ENCLOSURE 2 (Continued) | |||
REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 10 CFR 50.92 EVALUATION CONCLUSION Based on the preceding analysis, we have determined that the proposed change to the Technical Specifications will not significantly increase the probability er consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. It has been concluded that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve a significant hazards consideration. | |||
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0956m E2-2 06/14/88 SL-4744 | |||
_ _ _ _ _ _ _ _ _ _ _ _}} |
Latest revision as of 14:45, 16 December 2020
ML20195E524 | |
Person / Time | |
---|---|
Site: | Vogtle |
Issue date: | 06/14/1988 |
From: | Mcdonald R GEORGIA POWER CO. |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
Shared Package | |
ML20195E529 | List: |
References | |
SL-4744, NUDOCS 8806240073 | |
Download: ML20195E524 (6) | |
Text
'*' .
Goerp Powst Company
.
- t 3M P Wont Aseoue Myn, Gwq,a 30Y)3 bepoore 404 526 6526 UWg Arcsi PvA Ctf.ce Sex 4545 Ms ta. Gectg a 3%02 R. P. Mcdonald tre soutNvn ewinc systern E>ecutwe V ce Pres de-t PL Jear Cwatmc SL-4744 0956m X7G;17-V600 June 14, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIF1f.ATION 6.3 - TRAINING Gentlemen:
In accordance with 10 CFR 5').90 as required by 10 CFR 50.59(c)(1),
Georgia Power Company (GPC) hereby proposes to amend the Vogtle Electric Generating Plant Unit 1 Technical Specifications, Appendix A to Operating License NPF-68. .
The proposed amendment incorporates recent changes to 10 CFR 55 into the licensing program.
Enclosure 1 provides a detailed description of the proposed changes and the bases for the changes.
l Enclosure 2 details the basis for our determination that the proposed changes do not involve significant hazards considerations.
I Enclosure 3 provides instructions for incorporating the proposed changes into the Technical Specifications. The proposed correct page follows Enclosure 3.
In accordance with 10 CFR 170.12, a check for payment of the $150.00 license amendment filing fee is enclosed.
' l
' $lA Wi g, "8806240073 880614 PDR P
ADOCK 05000424 DCD b
[
t Georgia Power d U. S. Nuclear Regulatory Commission June 14, 1988 Page Two Mr. R. F. Mcdonald states that he is Executive Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
GEORGIA POWER COMPANY l
By: . N1 R. P. Mcdonald Sworn to and subscribed before me this 14th day of June,1988.
/ [1 Notary Public ner ND$
PAH/im
Enclosures:
- 1. Basis for Proposed Changes
- 2. 10 CFR 50.92 Evaluation
- 3. Instructions for Incorporation
- 4. Check No. 044779 for $150.00 filing fee c: Georaia Power Comoany Mr. P. D. Rice
! Mr. G. Bockhold, Jr.
GO-NORMS U. S. Nuclear Regulatory Commission i Dr. J. N. Grace, Regional Administrator i Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies) I Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle 0956m l
l
Georgia Power d ENCLOSURE 1 PLANT V0GTLE - UNIT 1 NRC COCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 BASIS FOR PROPOSED CHANGES PROPOSED CHANGE Revise Paragraph 6.3.1 to read as follows:
6.3 Trainina 6.3.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Plant Training and Emergency Preparedness Manager. Personnel will meet the minimum education and experience recommendations of ANSI N18.1-1971 and, for licensed staff,10 CFR 55.59 and the supplemental requirement specified in Sections A and C of Enclosure 1 of the . March 28, 1980 NRC lette' to all licensees, before they are considered qualified to perform all duties independently. Prior to meeting the recommendation of ANSI N18.1-1971, personnel may be trained to perform specific tasks and will be qualified to perform those tasks independently. Personnel who complete an accredited program which has been endorsed by the NRC shall meet the requirements of the accredited program in lieu of the above.
BA_SLS In Generic Letter 87-07, it was stated that the 55.59(c) content requirements (formerly Appendix A to 10 CFR 55) can be met with a performance-based program for a facility as approved by the NRC. In its :
Final Policy Statement on Training and Qualification of Nuclear Power l Plant Personnel, the Commission endorsed industry-accredited programs as !
performance based. l In the Federal Register Volume 52 No. 57 dated Wednesday, March 25, 1987, it was stated that:
"The requalification program must meet the requirements of paragraphs (c)(1) through (7) of this section. In lieu of paragraphs (c)(2), (3),
and (4) of this section, the Commission may approve a program developed by using a systems approach to training."
0956m El-1 06/14/88 SL-4744 i
Georgia Power d i
ENCLOSURE 1 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 BASIS FOR PROPOSED CHANGES The proposed change to the training sections reflects the sentiments of the Commission by allowing the use of a performance based industry-accredited program for training of the licensed staff.
0956m El-2 06/14/88 SL-4744
Georgia Power d ENCLOSURE 2 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 10 CFR 50 92 EVALUATION In accordance with 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment to the VEGP Unit 1 Technical Specifications and has determined that operation of the facility in accordance with the proposed amendment would not involve significant hazards considerations.
BACKGROUND The purpose of this technical specification change is to mirror the changes in requalification program requirements that recently appeared in the Code of Federal Regulations, Vol. 52 No. 57, Wednesday, March 25, 1987. The code now allows the Commission to approve a program developed by using a systems approach to training.
- 1. The proposed change does not significantly increase the probability or consequences of an accident previously evaluated. This change allows recognition # a training program that has received an NRC endorsement or approval. Since the plant operating staff will be "approved", the probability of any previously evaluated accident is not affected. The consequences of previously analyzed accidents are r.ot significantly increased.
- 2. The proposed change does not create the possibility of a new or different kind of accident than any accident previously evaluated.
The plant operating staff is still subject to an NRC approved program. A new or different failure mode should not result from the training given to the operating staff.
- 3. The proposed change does not involve a significant reduction in the margin of safety. Plant operations perunnel, both before and af ter the change, operated the plant subject to NRC review and approval of their training. In this case, the NRC is approving or endorsing a performance based training program. Safety margins are therefore not reduced since the operation . raining program is still subject to NRC 7
review and approval.
0956m E2-1 06/14/88 SL-4744
Georgia Power d ENCLOSURE 2 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATION 6.3 10 CFR 50.92 EVALUATION CONCLUSION Based on the preceding analysis, we have determined that the proposed change to the Technical Specifications will not significantly increase the probability er consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. It has been concluded that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve a significant hazards consideration.
I 1
l l
l I
0956m E2-2 06/14/88 SL-4744
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