ML20215A080
| ML20215A080 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/26/1986 |
| From: | CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | |
| Shared Package | |
| ML20215A010 | List: |
| References | |
| NUDOCS 8612110150 | |
| Download: ML20215A080 (11) | |
Text
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ATTACHMENT A APPLICATION FOR AMENDMENT TO CPERATING LICENSE i
Technical Specification Page Revisions l
4 Consolidated Edison Company of New York, Inc.
Indian Point Unit No. 1 Docket No. 50-03 Facility Operating License No. DPR-5 November, 1986 8612110150 DR 861126 ADOCK 05000003 PDR
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ATTACHMENT B i
i APPLICATION FOR AMENDMENT TO OPERATING LICENSE a
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Technical Specification Page Revisions
.t i-i Consolidated Edison Cotapany of New York, Inc.
Indian Point Unit No. 2 Docket No. 50-247
- Facility Operating License No. DPR-26 Novembe r, 1986 i
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VICE PRESIDENT ,
NUCLEAR POWEQ GENERAL GAANAGER GENERAL MANAGER GENERAL MANAGER GENERAL GAANAGER* :
NUCLEAR POWER ENVIROestAENTAL TECHNICAL AggggggSTRATIVE GENERATION HEALTN AND SAFETY SUPPORT SERVICES OPERATIONS RADeATION CNIEF PLANT MANAGER FN -
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- *Responedh tr the Fee Puencann Progren Acevans (CCR)-Cental Contal Rene Posten (S)-Canswous Sne C ras.
Figure 622 Facity Organization
COMPOSITION 6.5.1.2 The Station Nuclear Safety Committee shall, as a minimum, be composed as follows:
Chairman: General Manager-Technical Support Member: Chief Plant Engineer Membe r Operations Manager Membe r: Maintenance Manager Member: Instrument and Control Engineer Member Radiation Protection Manager Membe r: Reactor Engineer 6.5.1.2.1 In addition, other technically competent individuals may be appointed by the SNSC Chairman to serve as SNSC members.
ALTERNATES 6.5.1.3 Alternate membe rs shall be appointed in writing by the SNSC Chairman to serve on a tempora ry ba si s, and mu st have cualifications similar to the member being replaced.
MEETING FREQUENCY 6.5.1.4 The SNSC shall meet at lea st once per calendar month and as convened by the SNSC Chairman or his designated alternate.
QUORUM 6.5.1.5 A ouorum of the SNSC shall consist of the Chairman or his designated alterna te and four members. No more than two dlternates shall be included in the cuorum.
RESPONSIBILITIES 6.5.1.6 The Station Nuclear Safety Committee shall be re3ponsible fort
- d. Review of 1) all procedu re s required by Specification 6.8 and changes thereto, and 2) any other proposed procedu re s or changes thereto as determined by the Gene ral Manager-Technical Support to affect nuclea r sa fety.
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed change s to the Technical Specifications.
Amendment No. 6-6
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ATTACHMENT C 1
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Safety Assesament 1
i I-1 Consolidated Edison Company of New York, Inc.
Indian Point Unit Nos.1 and 2 Docket Nos. 50-03 and 50-247 Noveaber,1986
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Safety Assessment Discussion:
A proposed technical . specification revision is set forth in Attachments A and B to this application. Several changes are being initiated by Consolidated Edison to incorporate certain administrative changes to the Facility Organization. . The proposed revision is reflected in Figures 3.1 and 3.2 of the Indian Point Unit No.. 1 Technical Specifications and
- Figu res 6.2.1 and 6.2.2 of the Indian Point Unit No. 2 Technical Specifications. In addition, there is a proposed revision to Indian Point Unit No. 2 Technical Specification 6 5.1.2 which a s a result of the administrative changes to the Facility Organization reflects specific.
title changes to members of the Station Nuclear Safety Committee.
The proposed revision to Figures 3.1 and 3.2 and 6 2.1 and 6.2.2 reflect seve ral recent Consolidated Edison technical support organization and facility organization changes.
As a result of organizational restructuring the offsite Technical Support Organization is now known as the offsite Independent Safety Review and Audit Organization to better depict the current interface between offsite and onsite organizations. With the retirement of the position of Vice President of Nuclear Engineering and Quality Assu rance and Reliability the responsibilities were split between the Director of Power Generation Services taking over Quality Assurance and Reliability, offsite, and the Vice President of Nuclear Power taking over Nuclear Engineering, onsite.
As indicated in figu re s 3.1 and 6.2.1 the . Director of Quality Aasurance and Reliability now reports to the Director of Power Generation Services [
who in turn reports directly to the Executive Vice President of Central Ope ration s. This organizational split offsite and subsequent consolidation into existing organizations onsite permits Consolidated Edison to more effectively use it's personnel to both operate and support Indian Point. Altbough'not shown in figures 3.1 and 6.2.1, the offsite engineering and technical support re source s of the Executive Vice
, Pre sident of Central Operations continues to be provided in support of Indian Point.
The ' Nuclear Power Gene ra tion Department now includes an Operations Manager and staff instead of a Chief Operations Engineer, elimination of the position of Operations Superintendent and the addition of a new Planning and Project Manager and sta f f. The Ope ration s Manager is responsible for managing the activities of the Senior Watch Supervisors, the Support Facilitie s Supe rvisors, the rotating shifts and has additional personnel who a ssist in the day-to-day management of ope ra tions. Additional administrative staff sopport to the Operation s Manager continues to be provided by the Nuclear Power Generation Support Manager and staff. The Operations Manager is required to hold a Senior Reactor Operator's license for Indian Point Unit No. 2 and meet or exceed the minimum requirements of ANSI N18.1-1971 Section 4.2.2.
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The Projects and Planning Manager and staff organization includes the transfer of the Major Projects snager and staff from the Technical Support Depa rtment to the Nuclear Power Generdtjon Department.
The Nuclear Power Gene ration Depa rtment organizational changes a re intended to ensure that the operating personnel and their managers are not encumbered with staff duties, that they have the authority and responsibility to perform the operations and minor maintenance, and that they a re held accountable for the performance of their duties. The consolidation of Support and Planning organizations within Nuclear Power Generation further reduce the administrative burdens of the Operations W nager, Chief Technical Engineer to Chief Plant Engineer, Maintenance Manager and Instrument and Control Engineer.
All Fire Protection responsibilities of the Chief Technical Engineer of the Technical Support Depa rtment have been tra nsfe rred to the newly created position of Fire Protection, Safety and Security Manager of the Administrative Se rvice s Depa rtment. This reorganization raise s overall secu rity responsibilities to the Manager of Fire Protection, Safety and Security and tra n sfers them from the Security Administrator who is no longe r identified on Figu re 6.2.2. This organizational change consolidates and more clearly defines responsibilities as well as ensures that day to day administration of these areas do not conflict with the overall short and long term operation of these areas.
The proposed revision to the Facility Organization includes a change in the following titles; Maintenance Engineer to Maintenance Manager, Chief Technical Engineer to Chief Plant Enginee r, Radwaste Gene ral Supervisor to Radwa ste Manager, Te st and Performance Enginee r to Test and Pe rfomance Manager, Nuclea r Training Director to Nuclear Training Manager and Emergency Planning Director to Emergency Planning Manager.
The Nuclea r Environmental Monitoring Engineer and staff has become a functional responsibility and has been absorbed by the Manage r of Eme rgency Planning. The merging of Nuclear Environmental Monitoring under Emergency Planning permita a clearer direction of pe rsonnel who perform closely related functions in both emergency and non-emergency situations.
The Technical Support Depa rtment has been merged with the Nuclear Engineering Department resulting in the addition of the Safety Assessment and Nuclear Analysis Managers to the Technical Support Depa rtment. The long term goal of this merger is to have all 10 CFR 50.59 safety evaluation, radiological risk and fuel analysis and ra diological environmental technical specification work to originate f rom Indian Point permitting more effective use of personnel to suppcrt operation of Indian Point.
e Basis For No Significant Hazards Consideration Determination The proposed change does not involve a significant hazards consideration because operating of Indian Point Unit Nos. 1& 2 in accordance with this change would nots (1) involve a significant increa se in the probability or consequence s of an accident previously evaluated. This is an administrative change which reflects a recent facility re-organization with consolidation and reallignment of re spon sibilities. Therefore, this change cannot increase in the probability or consequences of an =acident.
(2) create the possibility of a new or different kind of accident f rom any previously analyzed. It has been determined that a new or different kind of accident will not be possible due to this change. An administrative change such as a facility re-organization does not create the possibility of a new or different kind of accident.
(3) invalve a significant reduction in a ma rgin of sa fety. The ddministrdtive Change as described above in the safety d ase ssment discu ssion has been determined not to impact the preservation or reduction of any margin of safety.
The Commission has provided guidance concerning the application of the standa rds for determining whether a significant ha za rd s considera tion exists by providing certain examples (48 FR 14870) of amendments that are con side red not likely to involve significant haza rds con side ra tion.
Example (f) relate s to a purely administrative change to Technical Specifications: for example, a change to achieve consistency throughout the Technical Specifications, correction of an e rror, or a change in nomenclatu re .
In this ca se , the proposed change described in Attachments A & B are related to Example (1), i.e., a purely administrative change.
The re fore , since the application for amendment involves a proposed change that is simila r to an example for which no significant ha za rds consideration exists, we have determined that the application involves no significant ha za rd s con side ra tion. The proposed changes have been reviewed by the Station Nuclear Safety Committee and the Nuclear Facility Safety Committee. The Committees concur that the se changes do not rep re sent a significa nt hazards considera tion and will not cause any change in the types or increase in the amounts of effluents or any change in the authorized power level of the facility.
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