ML20211L666

Amend 240 to License DPR-59,revises App A,Section 6 of Ts. Changes Will Enable Safety Review Committee to Review Rather than Audit Plant Staff Performance by Deleting Audit Requirement from Section 6.5.2.8

ML20211L666
Person / Time
Site:	FitzPatrick
Issue date:	10/03/1997
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20211L667	List: ML20211L666 ML20211L905
References
NUDOCS 9710100285
Download: ML20211L666 (7)

Text

_

i l

skmg g 3

UNITED STATES

~

{

}

NUCLEAR REGULATORY COMMISSION e

WASHINGTON. D.C. 3068H001

%,,,,,/

POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A-FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 240 License No. DPR-59 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated, April 14, 1997, complies with the i

standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will o)erate in conformity with the application, the provisions of t le Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not he inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

971010028S 971003 PDR ADOCK 05000333 P

PDR

~.. _

- -\\

(2) Technical Soecifications The Technical Specifications contained in A vendices A and B, as-revised through Amendment No. 240, are here)y incorporated in the

-icense.

The licensee shall operate the facility-in accordance with 4

.he Technical Specifications.

3.

This license amendment is effective as of the date of its issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/

/

S. Singh Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 3, 1997 y

ATTACHMENT TO LICENSE AMENDMENT NO. 240 L$1LITY OPERATING LICENSE NO. DPR-5_9_

DOCKET NO. 50-333

[

Revise Appendix A as follows:

Remove Paaes Insert Paaes 249 249 251 251 252 252 253 253 t

i I

i l

1 i

.. - - - ~ -

I.,

JAFNPP 6.5.1.'3 Allemales

- Altemative members shall be appointed in writing by the PORC Chairman to serve on a l

temporary basis, e

j 6.5.1.4 Meeting' Frequency -

1 Meetings will be called by the Chairman as the occasions for review or invesogation arise.

Meetings will be no less frequent than once a, month.

i 6.5.1.5 Quorum i

A quorum of the PORC shall consist of the Chairman or a Vice Chairman and five members -

including designated altomates. Vice-Chairmen may act as members when not acting as Chairman A quorum shall contain no more than two attemales.

6.5.1.6 Responsibilities The PORC shall be responsible for the:

~4 Review of 10 CFR 50.5g safety and environmentalimpact evaluations associated with a.

procedures and programs required by Specification 6.8, and changes thereto.

b.

Review of proposed tests and experiments that affect nuclear safety,

- Review of proposed changes to the Operating License and Technical Specifications.

c.

d.

Review of proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e.

Investigation of vietations of the Technical Specifications. The PORC shall prepare and present a report covering the evaluations and recommendations to prevent recurrence to the Site Executive Officer, who will then forward the report to the Chief Nuclear

- Officer, the Director Regulatory Affairs and Special Projects, and to the Chairman of the l

- Safety Review Committee.

f.

Review of plant operations to detect potential safety hazards.

g.

Performance of special reviews and/or investigations at the request of the Site j-Executive Officer, s

h.

Review of all reportable events.

i.

Review of the Process Control Program and the Offsite Dose Calculation Manual (ODCM) and changes thereto.

?'-

J.

Review the FitzPatrick Fire Protection Program and implementing procedures and changes thereto.

}

4 Amendment No, 99 6 7, 04, 170, 210, 220, 222, 220, 240 249

JAFNPP i

f.

Radiotopical safety

g. Mechanical engineering

h. Eleetrical engineering l.

Administrative controls and quality assurance practices

j. Environment

k. Civil / Structural Engineering 1.

Nuclear Licensing

m. Emergency Planning

n. Other appropriate fields associated with the ' unique characteristics of a nuclear power plant 4

CHARTER 6.5.2.2 The conduct of ths SRC will be in accordance with a charter approved by the Chief Nuclear Officer. The chaner will define the SRC's authority and establish the mechanism for carrying out its responsibilities.

MEMBERSHIP r

6.5.2.3 The SRC r.hali be composed of at least six individuals including a Chairman and a Vice Chairman. Members shall be appointed by the Director Regulatory Affairs and Special l

Projects and approved by the Chief Nuclear Officer. ERC members and attemates shall have an academic oegree in engineering or a physical science, or the equivalent, and shall have a minimum of five years technical experience in one or more areas listed in Section 6.5.2.1.

ALTERNATES 6.5.2.4 Altemates for the Chairman, Vice Chairman and members may be appointed in writing by the Director Regulatory Affairs and Special Projects and approved by the Chief Nuclear Officer.

l CONSULTANTS 6.5.2.5 Consultants may be used as determined by the SRC Chairman and as provided for in the charter.

MEETING FREQUENCY 6.5.2.6 The SRC shall meet at least once per six months.

4 Amendment No. 00,00,00,70,04,100,100, '.20,202,220,220, 240 251 i

i

4 a,

JAFNPP OUORUM 6.5.2.7 A Quorum shall consist of at least a majority of the appointed individuals (or their altemates) and the Chairman (or the designated altamate). No more than two alternates may participate as SRC voting members at any one time. No more than a minority of the quorum shall have direct line iesponsibility for the operation of the plant.

6.5.2.8 The SRC shall review:

a. The safety evaluation for 1) changes to procedures, equipment or systems and 2) tasts or experiments completed under the provision of Section 50.59,10 CFR, to verify that such l

actions did not constitute an unreviewed safety question.

l

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety i

question as defined in Section 50.59,10 CFR.

L l

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59,10 CFR.

d. Proposed changes to Technical Speelfications of this Operating License,

e. Violations of code, regulations, orders, Technical Specifications, license requirements, or of intamal procedures or instrections having nuclear safety significance, f.

Significant operating abnormr.lities or deviations from normal and expected performance of plant equipment that affect nuclear safety,

g. All Reportable Events.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety reisted structures, systems or components.

1.

Reports and meetings minutes of the Plant Operating Review Committee.

J. Plant staff performance.

l AUDLT 6.5.2.9 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 training and qualifications of the entire facility staff at least once per 12 months.

l I

Amendment No. - 50. 00. 05. ;00. ;10, 220, 240 252

5 JAFNPP

- 6.6 REDORTAoLE EVENT ACTION

' The following actions shall be taken forKeportable Events:

(A)

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and (B)

Each Reportable Event shall be reviewed by the PORC, and the results of this review shall be submitted to the Chief Nuclear omcor, the Director Regulatory Affairs and l

Special Projects, and the Chairman of the SRC.

- 6.7 - RAFETY LIMIT VIOL / TION (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)(1)(i).

(B)

An immet. ate report of each safety limit violation shall be made to the NRC by the -

Site Executive Officer. The Chief Nuclear Officer, the Director Regulatory Affairs and l

Special Projects, and the 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 component systems or structures and (3) correr.tive action required to prevent recurrence, The Site Executive Officer shall forward this repon to the Chief Nuclear Officer, the Director Regulatory Affairs and Special Projects, the Chairman of the SRC, and the l

NRC.

6.8 PROCEDURES (A)_ Written procedures and administrative policies shall be established, implemented, and maintained that:

1

1. meet or exceed the requirements and recommendations of Section 5 of ANSI 18.7-1972 " Facility Administrative Policies and Procedures."

2. are recommended in Appendix A of Regulatory Guide 1.33, November 1972.-

3. implement the Fire Protection Program.

4. include programs specified in Appendix B of the Radiological Effluent

- Technical Specifications, Section 7.2.

(B)

Each procedure of Specification 6.8.(A), and changes thereto, shall be appmved prior to implementation by the appropriate responsible member of management as-specified in Specification 6.5.0.

Amendment No. 50, 00, 00, 70. 00, ".'O, 220, 222, 220, 240 253

_ _ _ _ _ _ _ _ _ _