ML19209B594

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Proposed Tech Spec Changes to License DPR-64,consisting of Changes to Mgt Organization Charts & Position Titles.Safety Evaluation Encl
ML19209B594
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 10/02/1979
From: Early P
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19209B586 List:
References
NUDOCS 7910100202
Download: ML19209B594 (8)


Text

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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO MANACEMENT TITLE CHANGES (APPENDIX A)

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 SEPTEMBER 28 , 1979 1126 074 7910100 30L P

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PRESIDENT & '

CHIEF OPERATING

> 0FFICER S

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@i SAFETY REVIEW ,

y COMMITTEE 8

EXECUTIVE V.P. EXECUTIVE V.P.

& CHIEF 2NGINEER & DIRECTOR OF -l POWER OPERATIONS l

  • DIRECTOR OF SAFETY / SECURITY l l

MANAGER NUCLEAR OPERATIONS l I

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cn RESIDENT __ __ _j y, MANAGER

  • RESPONSIBLE FOR POWER AUTHORITY DIRECTION OF FIRE PROTECTION PROGRAF 1 bb ------------ADMINISTRATIVE FIGURE 6.2-1 CP' MANAGEMENT ORGANIZATION CHART FUNCTIONAL INDIAN POINT 3 NUCLEAR POWER PLANT a

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' TiUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b. The performance, training and qualifications of the entire facility staff at least once per 12 months.
c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
e. The Facility Emergency Plan and implementing procedures at least once per 24 months.
f. The Facility Security Plan and implementing procedures at least once per 24 months.
g. Any other area of facility operation considered appropriate by the SRC or the President. I
h. The Facility Fire Protection Program and implementing procedures at least once per two years.
i. A fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the President and Chief Operating Officer (to be refered to in the Tech. Spac. as President) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

Amendment No. 6-11 1126 076

RECORDS 6.5.2.10 Records will be maintained in accordance with ANSI 18.7-1972. The e following shall be prepared, approved and distrubuted as indicated below:

a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the President within 14 days after the date l of the meeting.
b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the President within }

14 days following completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the President and to the management positions I responsible for the :_eas audited within 30 days after completion of the aulit.

CHARTER 6.5.2.11 Conduct of the committee will be in accordance with a charter, approved by the President, setting forth the mechanism for implementation of the l committee's responsibilities and authority.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b. Each REPORTABLE OCCURRENCE requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PORC and a report sub-mitted by the Resident Manager to the Chairman of the SRC and Manager-Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36(c) (1) (i) .
b. The Safety Limit violation shall be reported immediately to the Commission. The Chairman of the SRC and Manager-Nuclear Operations will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. A Safety Limit Violation Report shall be prepared by the PORC.

This report shall describe (1) applicable circumstances preceding the occurrence, (2) effects of the occurrence upon facility com-ponents, systems or structures, and (3) corrective action taken to prevent recurrence.

Amendment No. 6-12 1126 077

ATTACHMENT II PROPOSED ENVIRONMENTAL TECHNICAL SPECIFICATION CHANGES MANAGEMENT TITLE CHANGES (APPENDIX B)

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 SEPTEMBER 28 , 1979 1126 078

e PRESIDENT & CHIEF OPERATING OFFICER W -

E 02 SAFETY REVIEW Ci COMMITTEE 5

EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT

& CHIEF ENGINEER & DIRECTOR OF POWER OPERATIONS DIRECTOR OF ENVIRONMENTAL PROGRAMS to STAFF

-- FIGURE 5.2-2 MANAGEMENT ORGANIZATION ENVIRONMENTAL rs) INDIAN POINT 3 NUCLEAR POWER PLANT Ch O

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4 ATTACHMENT III SAFETY EVALUATION RELATED TO MANAGEMENT TITLE CHANGES POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 SEPTEMBER 28, 1979 1126 080

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( Section I - Description of the Modification The position of General Manager and Chief Engineer has been retitled President and Chief Operating Officer. The position of Assistant General Manager-Engineering has been retitled Executive Vice President and Chief Engineer.

The position of Director of Power Operations has been changed to Executive Vice President and Director of Power Operations.

The Resident Managers will now report administratively to the Executive Vice President and Director of Power Operations.

The functional relationship between the Resident Manager and the Manager-Nuclear Operations remains unchanged.

Section II - Purpose of Modification The purpose of this modification is to comply with the require-ment of 10 CFR 50.59(c) to report all changes to the operating license.

Section III - Impact of the Change These changes in management titles will not alter the conclusion reached in the FSAR and SER Accident Analysis.

Section IV - Implementation of the Modification The modification as proposed will not impact the ALARA or Fire Protection Program at IP3.

Section V - Conclusions The incorporation of this modification: a) will not increase the probability nor the consequences of an accident or mal-function of equipment important to safety as previously evalu-ated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification.

Section VI - References (a) IP3 FSAR (b) IP3 SER 1126 081

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