. .

,'

ATTACHMENT I

PROPOSED TECHNICAL SPECIFICATION CHANGES

RELATED TO

MANACEMENT TITLE CHANGES

(APPENDIX A)

POWER AUTHORITY OF THE STATE OF NEW YORKINDIAN POINT 3 NUCLEAR POWER PLANT

DOCKET NO. 50-286SEPTEMBER 28 , 1979

1126 074

30L7910100

P

~ .

PRESIDENT &'

CHIEF OPERATING> 0FFICERSEto

@i SAFETY REVIEW ,

y COMMITTEE

8.

EXECUTIVE V.P. EXECUTIVE V.P.& CHIEF 2NGINEER & DIRECTOR OF -l

POWER OPERATIONS|

* DIRECTOR OFSAFETY / SECURITY |

|MANAGER

|NUCLEAR OPERATIONS

I

I

IRESIDENT __ __ _jcn

y, MANAGER

* RESPONSIBLE FOR POWER AUTHORITYDIRECTION OF FIRE PROTECTION PROGRAF 1

_-

bb ------------ADMINISTRATIVE FIGURE 6.2-1CP' MANAGEMENT ORGANIZATION CHART

FUNCTIONAL INDIAN POINT 3 NUCLEAR POWER PLANTa~<(J1

* *

' 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 containedwithin the Technical Specifications and applicable licenseconditions at least once per 12 months.

b. The performance, training and qualifications of the entirefacility staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurringin facility equipment, structures, systems or method of operationthat affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational QualityAssurance 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 leastonce per 24 months.

f. The Facility Security Plan and implementing procedures at leastonce per 24 months.

g. Any other area of facility operation considered appropriate bythe SRC or the President. I

h. The Facility Fire Protection Program and implementing proceduresat least once per two years.

i. A fire protection and loss prevention inspection and audit shallbe performed annually utilizing either qualified offsite licenseepersonnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss preventionprogram shall be performed by an outside qualified fire consultantat intervals no greater than 3 years.

AUTHORITY

6.5.2.9 The SRC shall report to and advise the President and Chief OperatingOfficer (to be refered to in the Tech. Spac. as President) on those areas ofresponsibility 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. Thefollowing shall be prepared, approved and distrubuted as indicated below:e

a. Minutes of each SRC meeting shall be prepared, approved andforwarded to the President within 14 days after the date |of the meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shallbe prepared, approved and forwarded to the President within }

14 days following completion of the review.

Audit reports encompassed by Section 6.5.2.8 above, shall bec.

forwarded to the President and to the management positions I

responsible for the :_eas audited within 30 days aftercompletion of the aulit.

CHARTER

6.5.2.11 Conduct of the committee will be in accordance with a charter, approvedby the President, setting forth the mechanism for implementation of the |

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 submittedpursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE requiring 24 hours notification tothe Commission shall be reviewed by the PORC and a report sub-mitted by the Resident Manager to the Chairman of the SRC andManager-Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION

6.7.1 The following actions shall be taken in the event a Safety Limit isviolated:

a. The reactor shall be shut down and reactor operation shall onlybe resumed in accordance with the provisions of 10 CFR 50.36(c) (1) (i) .

b. The Safety Limit violation shall be reported immediately to theCommission. The Chairman of the SRC and Manager-Nuclear Operationswill be notified within 24 hours.

c. A Safety Limit Violation Report shall be prepared by the PORC.This report shall describe (1) applicable circumstances precedingthe occurrence, (2) effects of the occurrence upon facility com-ponents, systems or structures, and (3) corrective action takento prevent recurrence.

Amendment No. 6-12

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ATTACHMENT II

PROPOSED ENVIRONMENTAL TECHNICAL

SPECIFICATION CHANGES

MANAGEMENT TITLE CHANGES

(APPENDIX B)

POWER AUTHORITY OF THE STATE OF NEW YORKINDIAN POINT 3 NUCLEAR POWER PLANT

DOCKET NO. 50-286SEPTEMBER 28 , 1979

1126 078

, .

e

PRESIDENT & CHIEFOPERATING OFFICER

$W -

E02 SAFETY REVIEWCi COMMITTEE

5.

EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT& CHIEF ENGINEER & DIRECTOR OF

POWER OPERATIONS

DIRECTOR OFENVIRONMENTAL

PROGRAMS

*.

to

STAFF

FIGURE 5.2-2--

MANAGEMENT ORGANIZATION ENVIRONMENTAL--

rs) INDIAN POINT 3 NUCLEAR POWER PLANTCh

O'WNC

. -

#

4

ATTACHMENT III

SAFETY EVALUATION

RELATED TO MANAGEMENT

TITLE CHANGES

POWER AUTHORITY OF THE STATE OF NEW YORKINDIAN POINT 3 NUCLEAR POWER PLANT

DOCKET NO. 50-286SEPTEMBER 28, 1979

.

1126 080

..

{.

( Section I - Description of the Modification

The position of General Manager and Chief Engineer has beenretitled President and Chief Operating Officer. The positionof Assistant General Manager-Engineering has been retitledExecutive Vice President and Chief Engineer.

The position of Director of Power Operations has been changedto Executive Vice President and Director of Power Operations.The Resident Managers will now report administratively to theExecutive Vice President and Director of Power Operations.The functional relationship between the Resident Manager andthe 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 operatinglicense.

Section III - Impact of the Change

These changes in management titles will not alter the conclusionreached in the FSAR and SER Accident Analysis.

Section IV - Implementation of the Modification

The modification as proposed will not impact the ALARA orFire Protection Program at IP3.

Section V - Conclusions

The incorporation of this modification: a) will not increasethe 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 thepossibility for an accident or malfunction of a different typethan any evaluated previously in the Safety Analysis Report;and c) will not reduce the margin of safety as defined in thebasis for any Technical Specification.

Section VI - References

(a) IP3 FSAR

(b) IP3 SER

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1126 081.