ML040750460

Amendments, Transfer of Administrative Controls Related to Quality Assurance

ML040750460
Person / Time
Site:	Saint Lucie
Issue date:	03/11/2004
From:	Moroney B NRC/NRR/DLPM/LPD2
To:	Stall J Florida Power & Light Co
Moroney B, NRR/DLPM, 415-3974
Shared Package
ML040750518	List: ML040750460 ML040760339 ML040760345
References
TAC MC1514, TAC MC1515
Download: ML040750460 (11)

Text

March 11, 2004 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING TRANSFER OF ADMINISTRATIVE CONTROLS RELATED TO QUALITY ASSURANCE FROM THE TECHNICAL SPECIFICATIONS TO THE QUALITY ASSURANCE PLAN (TAC NOS. MC1514 AND MC1515)

Dear Mr. Stall:

The Commission has issued the enclosed Amendment Nos. 189 and 133 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2. These amendments consist of changes to the Technical Specifications in response to your application dated November 21, 2003.

These amendments allow transfer of St. Lucie Units 1 and 2 Technical Specifications 6.5 (Review and Audit), 6.8.2 and 6.8.3 (Procedures and Programs Review Specifics), and 6.10 (Record Retention) to the St. Lucie Plants Quality Assurance Plan (a licensee-controlled document).

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 189 to DPR-67

2. Amendment No. 133 to NPF-16

3. Safety Evaluation cc w/enclosures: See next page

March 11, 2004 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING TRANSFER OF ADMINISTRATIVE CONTROLS RELATED TO QUALITY ASSURANCE FROM THE TECHNICAL SPECIFICATIONS TO THE QUALITY ASSURANCE PLAN (TAC NOS. MC1514 AND MC1515)

Dear Mr. Stall:

The Commission has issued the enclosed Amendment Nos. 189 and 133 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2. These amendments consist of changes to the Technical Specifications in response to your application dated November 21, 2003.

These amendments allow transfer of St. Lucie Units 1 and 2 Technical Specifications 6.5 (Review and Audit), 6.8.2 and 6.8.3 (Procedures and Programs Review Specifics), and 6.10 (Record Retention) to the St. Lucie Plants Quality Assurance Plan (a licensee-controlled document).

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 189 to DPR-67

2. Amendment No. 133 to NPF-16

3. Safety Evaluation cc w/enclosures: See next page Distribution:

Public PDII-2 R/F BMoroney OGC RidsNrrDlpmDpr LMiller ACRS RidsNrrDlpmLpdii (EHackett) BClayton (hard copy) TBoyce RidsNrrDlpmLpdii-2 (WBurton) GHill (4 paper copies) JMunday Package: ML040750518 Enclosure 1: Enclosure 2:

ADAMS No.: ML040750460 NRR-058 OFFICE LPD2-2/NSIP LPD2-2/PM LPD2-2/LA IROB/SC OGC LPD2-2/SC NAME LMiller BMoroney BClayton TBoyce LZaccari WBurton DATE 3/11/04 3/10/04 3/11/04 2/27/04 3/4/04 3/11/04 Package: ML040750518 OFFICIAL RECORD COPY

Florida Power and Light Company ST. LUCIE PLANT cc:

Senior Resident Inspector Mr. G. L. Johnston St. Lucie Plant Plant General Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6351 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mr. Terry L. Patterson Division of Emergency Preparedness Licensing Manager Department of Community Affairs St. Lucie Nuclear Plant 2740 Centerview Drive 6351 South Ocean Drive Tallahassee, Florida 32399-2100 Jensen Beach, Florida 34957 M. S. Ross, Attorney Vice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 P.O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Mr. Douglas Anderson Vice President - Nuclear Engineering County Administrator Florida Power & Light Company St. Lucie County P.O. Box 14000 2300 Virginia Avenue Juno Beach, FL 33408-0420 Fort Pierce, Florida 34982 Mr. J. Kammel Mr. William A. Passetti, Chief Radiological Emergency Department of Health Planning Administrator Bureau of Radiation Control Department of Public Safety 2020 Capital Circle, SE, Bin #C21 6000 SE. Tower Drive Tallahassee, Florida 32399-1741 Stuart, Florida 34997 Mr. William Jefferson, Jr.

Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957

FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 189 Renewed License No. DPR-67

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company (the licensee), dated November 21, 2003 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 Commissions regulations; D. The issuance of this amendment will not be inimical to the common 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 Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, Renewed Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 189, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William F. Burton, Acting Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 11, 2004

ATTACHMENT TO LICENSE AMENDMENT NO. 189 TO FACILITY RENEWED OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following pages of the St. Lucie Unit 1 Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Pages Insert Pages XIV XIV XV XV 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-20 6-20 6-21 6-21

FLORIDA POWER & LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST. LUCIE PLANT UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 133 Renewed License No. NPF-16

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company, et al. (the licensee), dated November 21, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 Commissions regulations; D. The issuance of this amendment will not be inimical to the common 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 Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, Renewed Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 133, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William F. Burton, Acting Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 11, 2004

ATTACHMENT TO LICENSE AMENDMENT NO. 133 TO FACILITY RENEWED OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following pages of the St. Lucie Unit 2 Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Pages Insert Pages XVIII XVIII XIX XIX 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-12a 6-12a 6-14 6-14 6-20e 6-20e 6-21 6-21

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 189 AND 133 TO FACILITY RENEWED OPERATING LICENSES NOS. DPR-67 AND NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.

ST. LUCIE PLANT, UNITS NOS. 1 AND 2 DOCKET NOS. 50-335 AND 50-389

1.0 INTRODUCTION

By letter dated November 21, 2003 (ML033300430), Florida Power and Light Company (FPL, the licensee) submitted proposed amendments to Renewed Operating Licenses DPR-67 and NPF-16 for St. Lucie Units 1 and 2, respectively. The proposed amendments would transfer St. Lucie Units 1 and 2 Technical Specifications (TSs) 6.5 (Review and Audit), 6.8.2 and 6.8.3 (procedures and programs review specifics), and 6.10 (Record Retention) to the St. Lucie Plants Quality Assurance Plan (QAP), a licensee-controlled document. The proposed amendments will reduce unnecessary regulatory burden for quality assurance program changes and result in more efficient use of FPL and U. S. Nuclear Regulatory Commission (NRC) resources.

2.0 REGULATORY EVALUATION

Regulatory requirements for items that must be included in the TSs are contained within Part 50, Section 36 of Title 10 of the Code of Federal Regulations (10 CFR 50.36), Technical Specifications. The TSs are to include items in the following five categories: safety limits, limiting conditions of operation, surveillance requirements, design features, and administrative controls. Four criteria provided in 10 CFR 50.36(c)(2)(ii) are used to determine if an item should be included within the TSs. Items satisfying any of the four criteria must be retained in the TSs, however, items not meeting any of the four criteria may be relocated from the TSs to a licensee-controlled document. The four criteria are listed below:

Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

Criterion 2: A process variable design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Criterion 3: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or present a challenge to the integrity of a fission product barrier.

Criterion 4: A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

The result of the proposed change is the relocation of TS Sections 6.5, 6.8.2, 6.8.3, and 6.10 from St. Lucie Units 1 and 2 TSs to the St. Lucie Plants QAP, which is incorporated into the Updated Final Safety Analysis Report and the Topical Quality Assurance Report. The relocation of this information maintains consistency with NUREG-1432, Standard Technical Specifications, Combustion Engineering (CE) Plants, and NRC Administrative Letter (AL) 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance. AL 95-06 provides relocation guidance for transferring TS administrative controls related to quality assurance to a licensee-controlled document. AL 95-06 states that the quality assurance program is a logical place for relocation due to the controls imposed by such regulations as Appendix B to 10 CFR Part 50, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, the existence of NRC-approved QAPs and licensee commitments to industry quality assurance standards, and the established QAP change control process in 10 CFR 50.54(a), Conditions of Licenses. AL 95-06 specifically identifies the administrative controls the licensee seeks permission to transfer to the QAP (TS review and audit provisions, processes for procedure reviews, and records retention) as examples of administrative controls that may be transferred to the QAP. Relocating the aforementioned administrative controls is consistent with NUREG-1432, which does not include administrative controls related to quality assurance in the CE standard TS requirements.

NUREG-1432 provides generic guidance for requirements that must remain in CE plants TSs.

3.0 TECHNICAL EVALUATION

TS Sections 6.5, 6.8.2, 6.8.3, and 6.10 are administrative programs. Section 6.5, Review and Audit, deals with facility review and audit procedures, specifically, describing the function and responsibility of the Facility Review Group and the Company Nuclear Review Board.

Section 6.8.2, Review and Approval Procedures, instructs how the specification review and approval process is to be conducted. Changes to Procedures, Section 6.8.3, demonstrates the process for permanent and temporary procedure changes. Section 6.10, Record Retention, defines the information that should be retained and the minimum period the information should be retained.

The TS sections to be relocated do not cover installed instrumentation used to detect and indicate a significant degradation of the reactor coolant pressure boundary, therefore, Criterion 1 does not apply.

The TS sections to be relocated do not satisfy Criterion 2 because they are not a design basis accident or transient analysis initial condition (design feature, operating restriction, or process variable) that either assumes the failure of or challenges the fission product barrier integrity.

The TS sections to be relocated do not satisfy Criterion 3 because they are not a primary success path component, structure, or system that serves to mitigate a design basis accident or transient that either assumes the failure of or challenges the fission product barrier integrity.

The TS sections to be relocated do not satisfy Criterion 4 because they are not a component, structure, or system significant to public health and safety based on operating experience or probabilistic safety assessment.

Based on the discussion above, TS Sections 6.5, 6.8.2, 6.8.3, and 6.10 requirements do not satisfy the 10 CFR 50.36(c)(2)(ii) criteria. Therefore, TS 6.5, 6.8.2, 6.8.3, and 6.10 may be relocated to other licensee-controlled documents, specifically, the St. Lucie Plants QAP. All changes to the QAP are made in accordance with 10 CFR 50.59, Changes, Tests, and Experiments and 10 CFR 50.54(a), Conditions of Licenses, Quality Assurance Criteria, to ensure an appropriate level of control. Therefore, the proposed changes are acceptable.

4.0 STATE CONSULTATION

Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.

5.0 ENVIRONMENTAL CONSIDERATION

These amendments relate to changes in record keeping, reporting, or administrative procedures or requirements. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 698, dated January 6, 2004). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Leslie S. Miller Date: March 11, 2004