ML003694423
| ML003694423 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/22/2000 |
| From: | Minns J NRC/NRR/DLPM |
| To: | NRC/NRR/DLPM |
| Minns J | |
| References | |
| TAC MA8327 | |
| Download: ML003694423 (4) | |
Text
March 22, 2000 MEMORANDUM TO: Biweekly Notice Coordinator FROM: John L. Minns, Project Manager /RA/
Decommissioning Section Project Directorate IV & Decommissioning Division of Licensing Project Management
SUBJECT:
REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE -
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING (TAC NO. MA8327)
Consolidated Edison Company of New York, Inc., Docket No.50-003, Indian Point Nuclear Generating Station, Unit 1, Buchanan, New York Date of application for amendment: February 14, 2000 Description of amendment request: The proposed amendment would revise Technical Specifications Sections 2.10.2, 3.1.2, 3.2.1, 4.1.8.1.b, and 4.1.8.1. Specifically, Sections 3.1.2, 3.2.1, and 4.1.8.1.b, are organizational title changes that are administrative in nature and reflect a streamlining of the Consolidated Edison Company of New York, Inc.'s, management structure. Section 4.1.8.1 is changed to reference the current sections of Part 20 of Title 10 of the Code of Federal Regulations (10 CFR) and to remove any ambiguity that may exist by referring to obsolete sections of the regulations. A footnote was moved from Section 2.11 to Section 2.10.2.6 to improve the clarity of the Technical Specification since it pertains to text in subsection 2.10.2.4.
Basis for proposed no significant hazards determination: As required by 10 CFR 50.91(a),
the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below.
Biweekly Notice Coordinator a) Changes To Sections 3.1.2, 3.2.1, and 4.1.8.1.b To Reflect Organizational Title Changes
- 1) Does the proposed license amendment involve a significant increase in the probability or in the consequences of an accident previously evaluated?
No. The proposed change is administrative in nature. The changes involve updating Sections 3.2.1.h and 4.1.8.b to use the title Shift Manager instead of Senior Watch Supervisor and updating Section 3.1.2 and 3.1.2.b to use the title Plant Manger instead of General Manger-Nuclear Power Generation and movement of the footnote, *Licensed Operator for IP2."
These changes do not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility. The Limiting Safety System Settings and Safety Limits specified in the current Technical Specifications remain unchanged. Therefore, the proposed changes would not involve a significant increase in the probability or in the consequences of an accident previously evaluated.
- 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
No. The proposed changes are administrative in nature. The safety analysis of the facility remains complete and accurate. There are no physical changes to the facility and the plant conditions for which the design basis accidents have been evaluated are still valid. The operating procedures and emergency procedures are unaffected. Consequently no new failure modes are introduced as a result of the proposed change. Therefore, the proposed changes would not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Does the proposed amendment involve a significant reduction in a margin of safety?
No. The proposed changes are administrative in nature. Since there are no changes to the operation of the facility or the physical design, the Updated Final Safety Analysis Report (UFSAR) design basis, accident assumptions, or Technical Specification Bases are not affected. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
b) Change To Section 4.1.8.1 To Reference The Current Sections Of 10 CFR 20
- 1) Does the proposed license amendment involve a significant increase in the probability or in the consequences of an accident previously evaluated?
No. The proposed change [to Section 4.1.8.1] is administrative in nature.
The change involves updating Section 4.1.8.1 to reference 10 CFR 20.1601(a) and 10 CFR 20.1601(b). This change does not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility. The Limiting Safety System Settings and Safety Limits specified in the current Technical Specifications remain unchanged. Therefore, the proposed change would not involve a significant
Biweekly Notice Coordinator increase in the probability or in the consequences of an accident previously evaluated.
- 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
No. The proposed change is administrative in nature. The safety analysis of the facility remains complete and accurate. There are no physical changes to the facility and the plant conditions for which the design basis accidents have been evaluated are still valid. The operating procedures and emergency procedures are unaffected. Consequently no new failure modes are introduced as a result of the proposed change. Therefore, the proposed change would not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Does the proposed amendment involve a significant reduction in a margin of safety?
No. The proposed change is administrative in nature. Since there are no changes to the operation of the facility or the physical design, the Updated Final Safety Analysis Report (UFSAR) design basis, accident assumptions, or Technical Specification Bases are not affected. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
Attorney for Licensee: Brent L. Brandenburg, Esq., Consolidated Edison Co. of New York, Inc., 4 Irving Place-1830, New York, NY 10003.
NRC Section Chief: Mike Masnik
Biweekly Notice Coordinator March 22, 2000 increase in the probability or in the consequences of an accident previously evaluated.
- 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
No. The proposed change is administrative in nature. The safety analysis of the facility remains complete and accurate. There are no physical changes to the facility and the plant conditions for which the design basis accidents have been evaluated are still valid. The operating procedures and emergency procedures are unaffected. Consequently no new failure modes are introduced as a result of the proposed change. Therefore, the proposed change would not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Does the proposed amendment involve a significant reduction in a margin of safety?
No. The proposed change is administrative in nature. Since there are no changes to the operation of the facility or the physical design, the Updated Final Safety Analysis Report (UFSAR) design basis, accident assumptions, or Technical Specification Bases are not affected. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
Attorney for Licensee: Brent L. Brandenburg, Esq., Consolidated Edison Co. of New York, Inc., 4 Irving Place-1830, New York, NY 10003.
NRC Section Chief: Mike Masnik DISTRIBUTION: File Center PDIV-D r/f OGC To receive a copy of this document, indicate "C" in the box OFFICE PDIV-D/PM C PDIV-D/LA C PDIV-D/SC NAME JMinns:sp DJohnson MMasnik DATE 3/20/00 3/20/00 3/22/00 DOCUMENT NAME:G:/PDIV-3/ip1/BWN-8327.WPD OFFICIAL RECORD COPY