ML19290B708

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Proposed Tech Specs Changes Re Safety Review Committee
ML19290B708
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/06/1979
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
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ML19290B704 List:
References
NUDOCS 7912130550
Download: ML19290B708 (8)
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Text

ATTACHMENT I PROPOSED TECHNICAL SPECIF CATIONS CHANGES RELATED TO SAFETY REVIEW COMMITTEE (APPENDIX A)

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 JDECEMBER 6, 1979 1553 235 7912130550

8. Review the Emergency Plan and implementing pro-cedures annually.
9. Perform special review and/or investigations at the request of the Resident Manager.
10. Review of those reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC, in accordance with Specification 6.9.

(F) Authority The PORC shall function tu advise the Resident Manager operations. The PORC shall recommend approval or disapproval to the Resident Manager of those items considered in 6.5 lE (1) through (4) and determine if items considered in 6.5 lE (1) through (5) consitute unreviewed safety questions, as defined in 10 CFR 50.59.

In the event of a disagreement between the PORC and the Resident Manager, the Chairman of the SRC and the Manager -

Nuclear Operations or their designated alternates shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and written notification provided on the next business day; however, the Resident Manager shall have responsibility for resolution of such disagreement pur-suant to Section 6.1 (G) Records Minutes of all meetings of the PORC shall be recorded and numbered. Copies will be retained in file. Copies will be forwarded to the Chairman of the SRC and the Manager -

Nuclear Operations.

(H) Frocedures Conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the per-tinent Administrative Procedures.

6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION 6.5.2.1 The SRC shall collectively have the competence required to review problems in the following areas:

a. Nuclear power plant operations
b. Nuclear engineering 1553 236
c. Chemistry and radiochemistry
d. Metallurgy
e. Instrumentation and control Amendment No. 250
f. Radiological safety
g. Mechanical engineering i
h. Electrical engineering
i. Administrative controls and quality assurance '

practices

j. Environment
k. Civil / Structural Engineering
1. Other appropriate fields associated with the unique characteristics of a nuclear power plant.
m. Licensing MEMBERSHIP 6.5.2.2 The SRC shall be composed of the following voting  ;

members:

Chairman: Principal Nuclear Engineer - Staff Vice-Chairman: Director - Quality Assurance l Member: Principal Nuclear Engineer - Projects Member:

Radiological Engineer Member: Manager - Nuclear Operations i Member: Principal Electrical Engineer - Staff ,

Member: Director of Environmental Programs i Member: Principal Civil /Siructural Engineer i Member: Principal Mechanical Engineer - Staff l Member: Nuclear Engineer - Staff (Secretary i of SRC)

Member: Principal Inservice Inspection Engineer -

Nuclear Operations Member: Licensing Supervisor Member: Senior Nuclear Engineer - Staff ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by  ;

the SRC Chairman; however, no more than two alternate shall l participate as voting members in SRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.

MEETING FR20UENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following initial fuel loading and at least once per six months, thereafter.

Amendment No. 251

QUORUM i

6.5.2.6 A quorum of SRC shall consist of the Chairman or Vice-Chairman and six members, including a_ternates. No more than minority of the quorum shall have a direct line responsibility for the operation of the plant.

REVIEW l 6.5.2.7 The SRC shall review: ,

a. The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments com-pleted under the provision of Section 50.59, ,

10 CFR, to verify that such actions did not constitute  !

an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c. Proposed tests or experiments which involve an un-reviewed safety question as defined in Section 50.59, 10 CFR.
d. Proposed changes to Technical Specifications of this Operating License,
e. Violations of code, regulations, orders, Technical  !

Specifications, license requirements, or of internal i procedures or instructions having nuclear safety significance. i

f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.  ;
g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the i

~

Commission.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components. l
i. Reports and meetings minutes of the Plant Operating l Review Committee.

t AUDIT ,

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

a. The conformance of facility operation'to provisions  ;

contained within the Technical Specifications and i dpplicable license Conditions at least once per 12 months.

1553 238

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

Amendment No. 252

I

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 Opera-  ;

tional 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,
h. The Facility Fire Protection Program and implementing procedures at least once per two years.
i. A independent fire protection and loss of 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 on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

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

a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the President within 14 days after the date 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. Audits reports encompassed by Section 6.5.2.8 above, shall be forwarded to the President and to the management positions responsible for the areas audited with 30 days after completion of the audit.

Amendment No. 252a

CHARTER e

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

6.6 REPORTABLE OCCURRENCE ACTION (A) In the event of a Reportable Occurrence, the NRC 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 NRC shall be reviewed timely by the PORC and a report submitted by the Resident Manager to the Manager-Nuclear Operations and the SRC.

6.7 SAFETY LIMIT VIOLATION (A) If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36 (c) (i).

(B) An immediate report of each safety limit violation shall be made to the NRC by the Resident Manager. The Manager -

Nuclear Operations and Chairman of the SRC 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) The PORC shall prepare a complete investigative report of each safety limit violation and include appropriate analysis and evaluation of: (1) applicable circumstances preceding the occurrence, (2) effects of the occurrence upon facility components systems or structures and (3) corrective action required to prevent recurrance. The Resident Manager shall forward this report to the Manager-Nuclear Operations, Chairman of the SRC and the NRC.

6.8 PROCEDURES (A) Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5 " Facility Administrative Policies and Procedures" of ANSI 18.7-1972 and Appendix A of Regulatory Guide 1.33, November 1972. In addition, procedures shall be established, implemented and maintained for the Fire Protection Program.

(B) Those procedures affecting nuclear safety shall be reviewed by PORC and approved by the Resident Manager prior to implementation.

(C) Temporary changes to nuclear related procedures may be made provided:

1. The intent of the original procedure is not altered.

Amendment No. 1553 2402s3

O ATTACHMENT II SAFETY EVALUATION RELATED TO SRC MEMBERSHIP 1553 241 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DECEMBER 6, 1979

I Section I - Description of the Modification The entire Section 6.5.2 of the Administrative Control Section of the JAF Technical Specification concerning the Safety Review Committee (SRC) has been deleted and a new Section 6.5.2 substituted which is identical with the Section 6.5.2 of the IP3 Technical Specification. This new Section 6. 5.2 is compatible with the format of the GE Boiling Water Reactor Standard Technical Specification.

Section II - Purpose of Modification The purpose of this modification is to bring Sectien 6.5.2 of the Administrative Control Section of the JAF Technical 9pecification into agreement with both the IP3 and the GE Boiling Water Reactor Standard Technical Specification because there is only one SRC at the Authority which has been constituted perform the same functions for both plants.

Section III - Impact of the Change This change is the wording of Section 6.5.2 (SRC) will not alter the conclusion reached in the FSAR and SER Accident Analysis.

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

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 Analyses Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification.

Section VI - References (a) JAF FSAR (b) JAF SER

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