ML20058Q160

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Proposed Tech Specs Section 6.5.2 Re Safety Review Committee
ML20058Q160
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/18/1993
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20058Q071 List:
References
JPTS-93-018, JPTS-93-18, NUDOCS 9310260094
Download: ML20058Q160 (7)
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Text

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ATTACHMENT I (JPN-93-076) 9 PROPOSED TECHNICAL SPECIFICATION CHANGE SAFETY REVIEW COMMITTEE '

JPTS 018 L

i New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 9310260094 93101B E; L,

PDR ADOCK 05000333 Ls; P PDR

JAFNPP

. f. Radiological safety

g. Mechanical engineering
h. Electrical engineering
i. 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 MEMBERSHIP 6.5.2.2 The SRC shall be composed of the following voting members:

Chairman: Manager-Nuclear Safety Evaluation Vice-Chairman: Vice President-Appraisal and Compliance Services Member: Vice President Nuclear Engineering Member: Vice President Nuclear Operations Member: Resident Manager-IP3 Member: Resident Manager-JAF Member: Consultant Member: Consultant ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC chairman. An Alternate Vice-Chairman shall be appointed in writing by the Executive Vice President - Nuclear Generation if necessary. However, no more than two altemates shall 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 FREQUENCY 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. 56, #d,h6,J6, M,100, 25,123.

251

JAFNPP  ;

6.5.2.10 RECORDS 1

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

a. Minutes of each SRC meeting shall be prepared and forwarded to the Executive Vice President-Nuclear Generation within 30 days after the date of the meeting,
b. Reports of review encompassed by Section 6.5.2.7 above shall be prepared and forwarded to the Executive Vice President-Nuclear Generation within 30 days following  ;

completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Nuclear Generation and to the management positions responsible for the areas audited within 30 days after completion of the audit. t t

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C Amendment No.K 252b

ATTACHMENT 11 (JPN-93-076)

SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGE SAFETY REVIEW COMMITTEE JPTS 018 New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333

4 SAFETY EVALUATION FOR JPTS-93-018 PROPOSED CHANGES TO SAFETY REVIEW COMMITTEE I. DESCRIPTION OF THE PROPOSED CHANGQS The proposed change will modify the membership of the Safety Review Committee (SRC), which is stated in Technical Specification 6.5.2.2., by:

  • Adding a second consultant, e Deleting references to the Vice President - Nuclear Support, and e naming the Vice President - Appraisal and Compliance Services to replace the Director - Quality Assurance as member and SRC Vice Chairman.

A change in record keeping requirements is also proposed. The time limit for providing the Executive Vice President-Nuclear Generation with meeting minutes and reports of review is changed from 14 days to 30 days.

11. PURPOSE OF THE PROPOSED CHANGES The proposed changes in membership are the result of several different and -

independent factors. The addition of a second consultant increases the Authority's flexibility to make use of expertise available in the industry, as needed, to address specific topics. Eliminating the position of Vice President - Nuclear Support (VP-NS) is the result of a proposed organization change in the Nuclear Generation Department (Reference 1). The groups previously reporting to the VP-NS will now be reporting to the Vice President - Nuclear Operations (VP-NO). Since the VP-NO is already assigned as an SRC member, the interests of those groups previously reporting to the VP-NS will still be represented. The third proposed change is intended to establish the SRC membership at a uniform management level. All SRC members, with the exception of consultants and the Director-Quality Assurance have a direct reporting ,

relationship to the Executive Vice President - Nuclear Generation (EVP). All SRC members, with the exception of consultants, the SRC Chairman, and the Director-Quality Assurance are at the vice president level. Elevating the quality assurance representation on SRC from the director level to the vice president level (Vice President - Appraisal and Compliance Services) will ensure that SRC activities receive appropriate management attention. ,

The proposed change concerning record keeping requirements is being made to provide a more achievable time frame for issuing records of SRC activities.

The change as proposed is consistent with the Standard Technical Specifications (Reference 2).

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4 111. EFFECT OF THE PROPOSED CHANGES l

The proposed changes represent minor adjustments in response to several factors.

The function of the SRC and responsibilities of individual SRC members remains unchanged. SRC activities will continue to be conducted in accordance with the -

provisions of ANSI N18.7 (Reference 3). In general, the preposed changes will have no measurable effect. The proposed change is administrative in nature and does not effect equipment or plant operation as described in the FSAR and SER.

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDER ATION Operation of the FitzPatrick plant in accordance with the proposed amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:

1. involve a significant increase in the probability or cons,equences of an accident previously evaluated.

The proposed change is purely administrative and does not involve plant equipment or operating parameters. There is no effect on any accident analysis assumptions or other conditions which could involve the probability or consequences of previously evaluated accidents.

2. create the possibility of a new or different kind of accident from those previously evaluated.

Since the proposed change is administrative in nature and does not involve hardware design or operation, it cannot create the possibility of a new or different kind of accident.

3. involve a significant reduction in the margin of safety.

The rolu of the Safety Review Committee as an independent reviewer of safety and regulatory aspects of plant operations remains unchanged. Specific responsibilities of the SRC as stated in Technical Specification subsection 6.5.2.7, remain unchanged.

V. IMEl,EMENTATION OF THE PROPOSED CHANGES The conduct of the SRC is governed by a written charter as required by T.S. 6.5.2.11.

SRC activities are performed in accordance with written procedures and administrative policies as required by T.S. 6.8 (A). The proposed changes, once approved, will be implemented by making appropriate changes to these written documents.

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VI. CONCLUSION The change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, the proposed change: '

1. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety ,

analysis report;

2. will not create the possibility for an accident or malfunction of a type different from any evaluated previously in the safety analysis report;
3. will not reduce the margin of safety as defined in the basis for any technical specification.

The proposed change involves no significant hazards consideration, as defined in 10 CFR 50.92. ,

Vll. FEFERENCES

1. NYPA Nuclear Safety Evalt ation, JAF-SE-93-075, Revision 0, " Organization Changes in the Nuclear Generation Department." -
2. NUREG 1433, " Standard Technical Specifications for GE Boiling Water Reactors, BWR/4," Revision 0, September 1992.
3. American National Standard ANSI N18.7 - 1972, " Administrative Controls for Nuclear Power Plants".
4. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report (FSAR), Section 13.2, " Organizational Structure and Responsibilities," and Section .

13.10 " Review and Audit of Operations," July 1993.

5. James A FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER).

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