ST-HL-AE-3630, Application for Amends to Licenses NPF-76 & NPF-80,changing Tech Spec 6.4.1 to Delete Ref to App a of 10CFR55 & Supplemental Requirements in Sections a & C of Encl 1 of H Denton Re Licensed Operator Retraining

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Application for Amends to Licenses NPF-76 & NPF-80,changing Tech Spec 6.4.1 to Delete Ref to App a of 10CFR55 & Supplemental Requirements in Sections a & C of Encl 1 of H Denton Re Licensed Operator Retraining
ML20066D526
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 01/08/1991
From: Kinsey W
HOUSTON LIGHTING & POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066D529 List:
References
ST-HL-AE-3630, NUDOCS 9101150133
Download: ML20066D526 (8)


Text

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llouston Lighting & Power January 08, 1991 ST IIL AE 3630 File No.: 009.06 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas. Project Electric Generating Station Units 1 and 2 Docket Nos. STN 50 498, STN 50 499 Proposed Amendr.ent to the Units 1 and 2 Technical Specification 6.4.1 llouston Lighting & Power Company (llL&P) proposes to amend Technical Specification 6.4.1 for the South Texas Project Electric Generating Station (STPECS) as shown in the attachments. This amendment would remove reference to Appendix A of 10CFR55 and the supplemental requirements in Sections A and C of Enclosure 1 of the March 28, 1980 letter from liarold Denton regarding Licensed Operator retraining to make the STPECS Technical Specifications consistent with regulatory language and format, liiM has reviewed the attached proposed amendment pursuant to 10CFR50.92 and determined that it does not involve a significant hazards consideration.

The basis for this determination is provided in the attachments. In addition, based on the information contained in this submittal and in the NRC Final Environmental Assessment for STPECS Units 1 and 2, itL&P has concluded that, pursuant to 10CFR51, there are no significant radiological or non-radiological impacts associated with the proposed action, and the proposed license amendment will not have a significant effect on the quality of the environment.

The STPECS Nuclear Safety Review Board has reviewed and approved the proposed changes.

In accordance with 10CFR50.91(b), liiAP is providing the State of Texas with a copy of this proposed amendment.

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.- hiouston Lighting & Power Company South Texas Project Electric Generating Station ST HL AE 3630 File No.: 009.06 Page 2

-If you should have any questions concerning this matter, ,ilease contact Mr. A. W. Harrison at (512) 972 7298 or myself at (512) 972-7921.

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. mi N, H Kinsey Vice President <

Nuclear Generation PLW/ amp Attachments: 1. Significant Hazards Evaluation for a Proposed Change in Training Requirements

2. Proposed Technical Specification 6.4.1 5

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Ilouston Lighting & Power Company ," { 06 South Texas Project Electric Generat ng Statw, n p,g, 3 CC; Regional Administrator, Region IV Rufus 5. Scott j Nuclear Regulatory Commission Associa~;e Ceneral Counsel '

611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P, O. Box 61367 Houston, TX 77208 Coorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 circle 75 Parkway J,.I. Tapia Atlanra, CA 30339 3064 Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Be11 pert Lane P, O. Box 910 Be .' 1p or t , NY 11713 Bay City, TX 77414 D. K. Lacker J. R Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Department of Health 1015 L Street, N,V, 1100 West 49th Street Washington, Oc 20036 Austin, TX 78756 3189 R. P. Verret/D, E. Ward Central Power & Light Company P.-O. Box 2121 Corpus Christi, TX 78403 J. C. Lanier/M B,-Lee City of /,ustin Electric Utility Department P.O. Box 1088 Austin, TX 78767 R J. Costello/M, T. Hardt City Public Service Board P, 0, Box 1771 San Antonio, TX_ 78296 Revised 10/08/90 L4/NRC/

4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter )

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llouston 1.ighting 6 Power ) Docket Nos. 50 498 Company, et al., ) 50 499

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South Texas Project )

Units 1 and 2 -)

AFFIDAVIT W, !!, Kinsey being duly sworn, hereby deposes and says that he is Vice President, Nuclear Generation, of Ilouston Lighting & Power Company; that he is duly authorize,d to sign and file with the Nuclear Regulatory Commission the attached proposed change to the South Texas Project Electric Generating Station Technical Specification 6,4,1 is familiar with the content thereof;

- and that the matters set forth therein are true and correct to the best of his knowledge and belief, N

Yu{j V, ll. Kinsey Vice President Nuclear Generation Subscribed and sworn to before me, a Notary Public in and for The State of Texas this l'O day of Juntar , 1991, I Ntk innAclD Notary gbblic in and for the State Texas

,, y* VICKY L WOMACh ri NcM Po%c State cd f em h My Cowe Eisres $1102

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1 ATTACllMENT'1 SIGNIFICANT.IIAZARDS EVALUATION FOR A PROPOSED CllANGE-IN TRAINING REQUIREMENTS i

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. 1 Attachment 1 ST HL.AE 3630 ,

Page 1 of 3 SIGNIFICANT HAZARDS EVALUATION FOR A PROPOSED CHANGE IN TRAINING REQUIREMENIS Bnckcround

' Technical Specification 6.4.1 (Training) currently states that:

A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Manager and shall meet or-exceed the requiremer.ts and recommendations of Section 5.5 of ANSI N18,1-1971 and Appendix A of 19 CFR Part 55 and the supplemental requirements specified in Sec.tvas A and C of Enclosure 1 of the March 28, 1980 NRC letter to 1 licensees, and shall include familiarization with relevant industry operational experience.

10 CFR Part 55 was revised in April,1987, and no lon6er contains an Appendix A.

The March 28, 1980 letter was issued by Mr. Harold Denton of the NRC, Sections A and C of Enclosure 1 to this letter provided supplemental requirements of a retraining and replacement training program for the unit

, staff. -The response to Question 1 of NUREC 1262, " Answers to Questions at Public Heetings Regarding Implementation of Title 10, Code of Federal-Regulations, Part 55 on Operators' Licenses," addresses supersession of training requirements-in the Denton letter by the new rule:

Q. 1. The Supplemental-Information-to NRC Ceneric Letter 87-07 states that, "These rules supersede all current regulations for operator licenses." Are training requirements from Mr H. R. Denton's March 28, 1980 letter superseded by the new rule?

A. Tho' rule supersedes all requirements where those requirements are less restrictivb, Where individual commitments aro more testrictive, you must follow those comp.'tments until you change then,

> Proposed Change This change deletes referenca to Appendix A'of 1C CFR Part 55 and the-supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter from Harold Danton.

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. i Attachment 1 ST HL AE 3630 Page 2 of 3 Safety Evaluation Reference to 10CFR55 Appendix A can be deleted because the current revised 10CFR55 addressed by the Licensed Operator Requalification Training Program does not include an Appendix A. Reference to the Denton March 28, 1980 letter can be deleted because its requirements have been superseded by the revised 10CFR55. The requirements of the revised rule take into account the requirements of the Denton letter.

The Licensed Operator Requalification Training Program has been reviewed and approved by the NRC (see NRC correspondence dated September 12, 1989) as having met the NRC's training requirements.

Determination of Sirnificant Hazards i Pursuant to 10CFR50.91, this analysis provides a determination that the proposed change to the Technical Specifications does not involve any significant hazards consideration as defined in 10CFR50.92,

1. The proposed change doer, not involve a 5si nificant increase in the probability or consequences of an accident previously evaluated.

Because no aspects of the STPEGS Operator Training Program that are important to safety are removed or diminished, the proposed amendment will not invocm a significant increase in the probability or consequences of any accident previously evaluated.

2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed amendment is administrative in nature and does not involve any changes to plant design or configuration or overall training of the plant operators. Therefore, the proposed change will not create the possibility of a new or different kind of accident.

3. The proposed change does not involve a significant reduction in the margin af safety. The proposed amendment does not remove or diminish any elements of the nuclear training program that are essential to the safe operation of STPEGS. It does not involve any changes to plant operating systems or associated safety analyses.

Th'refore, the proposed changes do not involve a significant reduction in the margin of safety.

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Attachment 1 ST.HL.AE 3630 i page 3 of 3 Conclusion f

The Commissi,,-. nas provided guidance concerning application of the standards for determining whether a significant hazards considetation exists.

This guidance includes exampics ($1FR77$0) of the t,se of amendments considered not likely to involve significant hazards considerations. The chante proposed is similar to the examples of administrative changes identified in 51FR7750 bect.use the proposed change is to make the Technical Specifications consistent with 10CFR55 as revised in April, 1987, t

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