ML013550131

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License Amendments 115 & 55, Updating Unit 1 Operating License and Adding to Unit 2 Operating License the Standard License Condition as Stated in Generic Letter 86-10, Section F
ML013550131
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/11/1992
From: Norris J
Office of Nuclear Reactor Regulation
To: Goldberg J
Florida Power & Light Co
References
TAC M81934, TAC M81935
Download: ML013550131 (38)
v • d • e


Text

LIC.EtSE AUTHORITYy HLE Ce-v. if June 11, 1992 Docket Nos. 50-335 and 50-389 Mr. J. H. Goldberg President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

Dear Mr. Goldberg:

SUBJECT:

ST. LUCIE UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: FIRE PROTECTION (TAC NOS. M81934 AND M81935)

The Commission has issued the enclosed Amendment Nos. 115 and 55 to Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications in response to your application dated October 17, 1991.

These amendments update the Unit 1 operating license and add to the Unit 2 operating license the standard license condition as stated in Generic Letter 86-10, Section F; revise the Unit 1 and Unit 2 Technical Specifications to delete Sections 3/4.3.3.7, 3/4.7.11, 3/4.7.12, and 6.2.2.e; and add Section 6.5.1.6.n. These amendments are in accordance with the guidelines stated in Generic Letter 88-12.

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,

/s/ by L. Raghavan/for Jan A. Norris, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 1 1 5 to DPR-67
2. Amendment No. 55 to NPF-16
3. Safety Evaluation cc w/enclosures:

See next page Document Name: SL81934.AMD

0 "UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 June 11, 1992 Docket Nos. 50-335 and 50-389 Mr. J. H. Goldberg President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

Dear Mr. Goldberg:

SUBJECT:

ST. LUCIE UNITS I AND 2 - ISSUANCE OF AMENDMENTS RE: FIRE PROTECTION (TAC NOS. M81934 AND M81935)

The Commission has issued the enclosed Amendment Nos. 115 and 55 to Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications in response to your application dated October 17, 1991.

These amendments update the Unit I operating license and add to the Unit 2 operating license the standard license condition as stated in Generic Letter 86-10, Section F; revise the Unit 1 and Unit 2 Technical Specifications to delete Sections 3/4.3.3.7, 3/4.7.11, 3/4.7.12, and 6.2.2.e; and add Section 6.5.1.6.n. These amendments are in accordance with the guidelines stated in Generic Letter 88-12.

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, L V t L RNAývAVw.

"+0fJan A. Norris, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No.l15 to DPR-67
2. Amendment No. 55 to NPF-16
3. Safety Evaluation cc w/enclosures:

See next page

Mr. J. H. Goldberg Florida Power and Light Company St. Lucie Plant cc:

Jack Shreve, Public Counsel Mr. Jacob Daniel Nash Office of the Public Counsel Office of Radiation Control c/o The Florida Legislature Department of Health and 111 West Madison Avenue, Room 812 Rehabilitative Services Tallahassee, Florida 32399-1400 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Senior Resident Inspector St. Lucie Plant Regional Administrator, RII U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7585 S. Hwy AlA 101 Marietta Street N.W., Suite 2900 Jensen Beach, Florida 33457 Atlanta, Georgia 30323 Mr. Robert G. Nave, Director Mr. R. E. Grazio Emergency Management Director, Nuclear Licensing Department of Community Affairs Florida Power and Light Company 2740 Centerview Drive P.O. Box 14000 Tallahassee, Florida 32399-2100 Juno Beach, Florida 33408-0420 Harold F. Reis, Esq.

Newman & Holtzinger 1615 L Street, N.W.

Washington, DC 20036 John T. Butler, Esq.

,.,Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 34982 Mr. James V. Chisolm, County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852

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  • ~0* UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No. DPR-67
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 October 17, 1991, complies with the 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 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, 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 2.C.(2) to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.115 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. In addition, license condition 2.C.(3) of Facility Operating License DPR-67 is amended to read as follows:*

(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility (The fire protection program and features were originally described in licensee submittals L-83-514 dated October 7, 1983, L-83-227 dated April 22, 1983, L-83-261 dated April 25, 1983, L-83-453 dated August 24, 1983, L-83-488 dated September 16, 1983, L-83-588 dated December 14, 1983, L-84-346 dated November 28, 1984, L-84 390 dated December 31, 1984, and L-85-71 dated February 21, 1985) and as approved in by NRC letter dated July 17, 1984 and supplemented by NRC letters dated February 21, 1985, March 5, 1987, and October 4, 1988 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

4. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1. Page 3 of License
2. Changes to the Technical Specifications Date of Issuance: June 11, 1992
  • Page 3 is attached, for convenience, for the composite license to reflect this page.

(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below; (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2700 megawatts (thermal), provided that the construction items, preoperational tests, startup tests, and other items identified in Enclosure 1 to this license have been completed as specified in Enclosure 1.

Enclosure 1 is an integral part of, and is hereby incorporated in this license.

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

(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility (The fire protection program and features were originally described in licensee sub mittals L-83-514 dated October 7, 1983, L-83-227 dated April 22, 1983, L-83-261 dated April 25, 1983, L-83-453 dated August 24, 1983, L-83-488 dated September 16, 1983, L-83-588 dated December 14, 1983, L-84-346 dated November 28, 1984, L-84-390 dated December 31, 1984, and L-85-71 dated February 21, 1985) and as approved in by NRC letter dated July 17, 1984 and supplemented by NRC letters dated February 21, 1985, March 5, 1987, and October 4, 1988 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 115

ATTACHMENT TO LICENSE AMENDMENT NO. 115 TO FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Pages Insert Pages 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-39 3/4 3-39 3/4 3-40 3/4 3-40 3/4 7-40 thru 3/4 7-45 B 3/4 3-3 B 3/4 3-3 B 3/4 7-7 6-2 6-2 6-5 6-5 6-8 6-8

1 DELETED ST. LUCIE - UNIT 1 3/4 3-37 Amendment No. 2 6,4 0 ,6 9 ,

115

DELETED ST. LUCIE - UNIT 1 3/4 3-38 Amendment No. 2-&,115

DELETED ST. LUCIE - UNIT 1 3/4 3-39 Amendment No. 2T,6 6 ,108, 115

DELETED Amendment No. 2 5,6 6,108, ST. LUCIE - UNIT 1 3/4 3-40 115

INSTRUMENTATION BASES 3/4.3.3.6 DELETED 3/4.3.3.7 DELETED 3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with the recommendations of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

ST. LUCIE - UNIT 1 B 3/4 3-3 Amendment No. 26,37,67, 115

INSTRUMENTATION BASES 3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/

trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monit6r and control, as applicable, the releases of radioactive materials in ga-seous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

ST. LUCIE - UNIT 1 B 3/4 3-4 Amendment No. 59 4

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant M1anager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence from the control room a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by the President Nuclear Division, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 An onsite and an offsite organi.Zation-shall be estdblished for unit operation and corporate management. This onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. Those relationships shall be documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented in'the Topical Quality Assurance Report and updated in accordance ;with 10 CFR 50.54(a)(3).
b. The President - Nuclear Division shall be responsible for overall plant nuclear safety. This individual shall take any measures~ineeded to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
c. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite resourdes necessary for safe operation and maintenance of the plant.
d. Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
e. Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the health physics manager shall have direct access to that onsite individual having responsibility for overall unit management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

ST. LUCIE - UNIT 1 6-1 Amendment No. , ?j 137,

6.0 ADMINISTRATIVE ATROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.
c. A health physics technician# shall be on site when fuel is in the reactor.
d. All CORE ALTERATIONS shall be observed by a licensed operator and supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

The SRO in charge of fuel handling normally supervises from the control room and has the flexibility to-directly supervise at either the refueling deck or the spent fuel pool.

  1. The health physics technician may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unex I pected absence, provided immediate action is taken to fill the required positions.

ST. LUCIE - UNIT 1 6-2 Amendment No. 18,26,65,69,93, 115

ADMINISTRATIVE CONTROL

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.
4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant Manager or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individ ual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

g. The Operations Supervisor shall hold a Senior Reactor Operator license.

SHIFT TECHNICAL ADVISOR 6.2.3 The Shift Technical Advisor function is to provide on shift advisory technical support in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

ST. LUCIE - UNIT I 6-5 Amendment No. 69,-9 115

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica tions of ANSI/ANS-3.l-1978 as endorsed by Regulatory Guide 1.8, September 1975 (reissued May 1977), except for (1) the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8., September 1975, and (2) the Shift Technical Advisor who shall have a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design and plant operating characteristics, including transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS-3.1 1978 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW GROUP (FRG)

FUNCTION 6.5.1.1 The Facility Review Group shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Facility Review Group shall be composed of the:

Member: Plant Manager Member: Operations Superintendent Member: Operations Supervisor Member: Maintenance Superintendent Member: Instrument & Control Supervisor Member: Reactor Supervisor Member: Health Physics Supervisor Member: Technical Supervisor Member: Chemistry Supervisor Member: Quality Control Supervisor Member: Assistant Plant Supt. Mechanical Member: Assistant Plant Supt. Electrical The Chairman shall be a member of the FRG and shall be designated in writing.

ST. LUCIE - UNIT 1 6-6 Amendment No. Z0,07.69

IADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the FRG Chair man to serve on a temporary basis; however, no more than two alternates shall participate as voting members in FRG activities at any one time.

MEETING FREQUENCY 6.5.1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.

_UORUM 6.5.1.5 The quorum of the FRG necessary for the performance of the FRG respons ibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Facility Review Group shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.
b. Review of all proposed tests and experiments that affect nuclear safety.
c. Review of all proposed changes to Appendix A Technical Specifications.
d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.
e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua tion and recommendations to prevent recurrence to the President Nuclear Division and to the Chairman of the Company Nuclear Review Board.
f. Review of all REPORTABLE EVENTS.
g. Review of unit operations to detect potential nuclear safety hazards.
h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the Company Nuclear Review Board.

ST. LUCIE -LUNIT I 6-7 Amendment No. 90, *p *h, 107,

ADMINISTRATIVE CONTROLa

i. Review-of the Security Plan and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.
j. Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.
k. Review of every unplanned on-site release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the President - Nuclear Division and to the Company Nuclear Review Board.
1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RADWASTE TREATMENT SYSTEMS.
m. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last FRG meeting.
n. Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a. Recommend in writing to the Plant Manager, approval or disapproval of items considered under Specifications 6.5.1.6.a through d above.
b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6 a, b, d, and e above constitutes an unreviewed safety question.
c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the President Nuclear Division and the Company Nuclear Review Board of disagreement between the FRG and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 6.5.1.8 The Facility Review Group shall maintain written minutes of each FRG meeting that, at a minimum, document the results of all FRG activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the President Nuclear Division and the Chairman of the Company Nuclear Review Board.

ST. LUCIE - UNIT 1 6-8 Amendment No. 69,*2,93,1,1 2,-,

115

UNITED STATES NUCLEAR REGULATORY COMMISSION D.C. 2055M 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 FACILITY OPERATING LICENSE Amendment No. 55

-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 October 17, 1991, complies with the 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 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, 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 2.C.2 to read as follows:
2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3. In addition, license condition 2.C.(20) of Facility Operating License NPF-16 is amended to read as follows:*

(20) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (The fire protection program and features were originally described in the Final Safety Analysis Report, and supplemented by licensee submittals L-82-282 dated July 14, 1982, L-83-89 dated February 25, 1983, L-83-425 dated July 22, 1983, L-83-603 dated December 27, 1983, L-84-347 dated November 28, 1984, L-84-389 dated December 31, 1984, and L-85-72 dated February 21, 1985 for the facility) and as approved in the NRC Safety Evaluation Report Supplement 3 dated April 1983 and supplemented by NRC letter dated December 5, 1986 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

4. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION i ~e *ow, N.Ber 0w4 Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1. Page 7a of License
2. Changes to the Technical Specifications Date of Issuance: June 11, 1992
  • Page 7a is attached, for convenience, for the composite license to reflect this page.

- 7a

19. Unit No. I spent fuel may be transferred from the Unit No. 1 spent fuel pool to the Unit No. 2 spent fuel pool, as necessary, until completion of all activities related to the increase in capacity of the Unit No. 1 spent fuel pool to 1706 spent fuel assemblies. Spent fuel assemblies transferred from the Unit 1 spent fuel pool to the Unit 2 spent fuel pool may remain in the Unit 2 spent fuel pool or be transferred back to the Unit 1 spent fuel pool.
20. Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (The fire protection program and features were originally described in the Final Safety Analysis Report, and supplemented by licensee submittals L-82-282 dated July 14, 1982, L-83-89 dated February 25, 1983, L-83-425 dated July 22, 1983, L-83-603 dated December 27, 1983, L-84-347 dated November 28, 1984, L-84-389 dated December 31, 1984, and L-85-72 dated February 21, 1985 for the facility) and as approved in the NRC Safety Evaluation Report Supplement 3 dated April 1983 and supplemented by NRC letter dated December 5, 1986 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 55

ATTACHMENT TO LICENSE AMENDMENT NO. 55 TO FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Pages Insert Pages 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-46 3/4 7-29* 3/4 7-29*

3/4 7-30 thru 3/4 7-40 B 3/4 3-3 B 3/4 3-3 B 3/4 7-7 B 3/4 7-7 B 3/4 7-8 6-2 6-2 6-9 6-9

  • This page has not been changed; it is included to maintain document completeness.

I DELETED ST. LUCIE - UNIT 2 3/4 3-44 Amendment No. 55

DELETED ST. LUCIE - UNIT 2 3/4 3-45 Amendment No. 46- 55

DELETED ST. LUCIE - UNIT 2 3/4 3-46 Amendment No. 4 6-, 55

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use ortransfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source or detector.

4.7.10.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

ST. LUCIE - UNIT 2 3/4 7-29

INSTRUMENTATION BASES 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

3/4.3.3.7 DELETED 3/4.3.3.8 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors,n May 1981.

3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/

trip setpoints for these instruments shall be calculated in accordance with the methodology in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

ST. LUCIE - UNIT 2 B 3/4 3-3 Amendment No. 55

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INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided I

and control, as applicable, the releases of radioactive materials to monitor effluents during actual or potential releases of gaseous effluents.in gaseous alarm/trip setpoints for these instruments shall be calculated The with the methodology in the ODCM to ensure that the alarm/trip in accordance will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation includes provisions for monitoring the concentrations of potentially also gas mixtures in the waste gas holdup system. The OPERABILITY explosive instrumentation is consistent with the requirements of General and use of this Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection excessive overspeed is required since excessive overspeed of from turbine the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

ST. LUCIE - UNIT 2 B 3/4 3-4 Amendment No. 25

PLANT SYSTEMS BASES SNUBBERS (Continued)

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc. . . ). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.

3/4.7.11 DELETED ST. LUCIE - UNIT 2 B 3/4 7-7 Amendment No. 55

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence-from the control room, a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by the President Nuclear Division, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.7.1 An onsite and an offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shali include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to andincluding all operating organization positions. Those relationships shall be documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented in the Topical Quality Assurance Report and updated in accordance with 10 CFR 50.54(a)($).
b. The. President - Nuclear Division shall be responsible for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and:-providing technical support in the plant so that continued nuclear safety is assured.
c. The, Plant Manager shall.be responsible for overall unit safe operation~and shall have control over thoseonsite-resources necessary for safe operation and maintenance of the plant.
d. Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organiza tional freedom to be independent from operating pressures.
e. Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the health physics manager shall have direct access" to that onsite individual having responsibility for overall unit management. Health physics personnel shall have the-authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

ST. LUCIE - UNIT 2 6-1 Amendment No. 1;,109 ;V, 47

ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-I.
b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.
c. A health physics technician# shall be on site when fuel is in the reactor.
d. All CORE ALTERATIONS shall be observed by a licensed operator and supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. The SRO in charge of fuel handling normally supervises from the control room and has the flexi bility to directly supervise at either the refueling deck or the spent fuel pool.
e. DELETED
f. Administrative procedures shall be developed and implemented to limit the-working hours of unit staff who perform safety-related functions;.e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

  1. The health physics technician may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

ST. LUCIE - UNIT 2 6-2 Amendment No. 29 55

ADMINISTRATIVE CON 'LS RESPONSIBILITIES (Continued)

k. Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the President Nuclear Division and to the Company Nuclear Review Board.
1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RADWASTE TREATMENT SYSTEMS.
m. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last FRG meeting.
n. Review of the Fire Protection Program and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specifications 6.5.1.6a. through d. and m. above.
b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6a, b, d and e above constitutes an unreviewed safety question.
c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the President Nuclear Division and the Company Nuclear Review Board of disagreement between the FRG and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 6.5.1.8 The Facility Review Group shall maintain written minutes of each FRG meeting that, at a minimum, document the results of all FRG activities performed under the responsibility and authority provisions of these technical specifica tions. Copies shall be provided to the President - Nuclear Division and the Chairman of the Company Nuclear Review Board.

6.5.2 COMPANY NUCLEAR REVIEW BOARD (CNRB)

FUNCTION 6.5.2.1 The Company Nuclear Review Board shall function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy ST. LUCIE - UNIT 2 6-9 Amendment No. 13,29,-47,6-3, 55

ADMINISTRATIVE CONTROLS FUNCTION (Continued)

e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices COMPOSITION 6.5.2.2 The President - Nuclear Division shall appoint, in writing, a minimum of five members to the CNRB and shall designate from this membership, in writing, a Chairman. The membership shall function to provide independent review and audit in the areas listed in Specification 6.5.2.1. The Chairman shall meet the requirements of ANSI/ANS-3.l-1987, Section.4.7.1. The members of the CNRB shall meet the educational requirements of the ANSI/ANS-3.l-1987, Section 4.7.2,. and have at least 5 years of professional level experience in one or more of the fields listed in Specification 6.5.2.1. CNRB members who do not possess the educational re.quirements of ANSI/ANS-3.l-1987, Section 4.7.2 (up to a maximum of 2 members) shall be evaluated, and have their membership approved and documented, in writing, on a case-by-case basis by the President - Nuclear Division, considering the alternatives to educational requirements of ANSI/ANS-3.l-1987, Sections 4.1.1 and 4.1.2.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in CNRB activities at any one time.

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

MEETING FREQUENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter and as convened by the CNRB Chairman or his designated alternate.

QUORUM 6.5.2.6 The quorum of the CNRB necessary for the performance of the CNRB review and'audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least a majority of CNRB members including alternates. No more than a minority of the quorom shall have line responsibility fbr operation of the unit.

ST. LUCIE - UNIT 2 6-10 Amendment No. 1;, 2/, *, ft, 47,

0* UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 115 AND 55 TO FACILITY OPERATING LICENSE NO. DPR-67 AND NO. NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.

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

1.0 INTRODUCTION

By letter dated October 17, 1991, the Florida Power & Light Company (FPL, the licensee) proposed changes to the Technical Specifications (TS) and Facility Operating Licenses DPR-67 and NPF-16 for the St. Lucie-Plant, Unit Nos. I and 2, respectively. The proposed changes would add and update the NRC standard fire protection license condition to each operating license, and relocate fire protection requirements from the TS to the Updated Final Safety Analysis Reports (UFSAR). The changes have been developed in accordance with the guidance contained in NRC Generic Letter (GL) 86-10, "Implementation of Fire Protection Requirements," and GL 88-12, "Removal of Fire Protection Requirements from the Technical Specifications."

Specifically, the requested changes would revise license condition 2.C.(3) for Unit 1 and add license condition 2.C.(20) for Unit 2 with the standard license condition as shown in GL 86-10, Section F. In addition, the proposed amendment would relocate the following to Appendix 9.5A of the UFSAR: TS 3/4.3.3.7, Fire Detection Instrumentation; TS 3/4.7.12, Penetration Fire Barriers; TS 6.2.2.e, Site Fire Brigade; and TS 6.5.1.6.n, Facility Review Group Responsibilities.

2.0 BACKGROUND

Following the fire at the Browns Ferry Nuclear Power Plant on March 22, 1975, the Commission undertook a number of actions to ensure that improvements were implemented in the Fire Protection Programs for all power reactor facilities.

Because of the extensive modification of the Fire Protection Programs and the number of open issues resulting from staff evaluations, a number of revisions and alterations occurred in these programs over the years. Consequently, licensees were requested by GL 86-10 to incorporate the final NRC-approved Fire Protection Program in their FSAR. In this manner, the Fire Protection Program -- including the systems, the administrative and technical controls, the organization, and other plant features associated with fire protection -

would have a status consistent with that of other plant features described in

the FSAR. In addition, the Commission concluded that a standard license condition, requiring compliance with the provisions of the Fire Protection Program as described in the FSARs, should be used to ensure uniform enforcement of fire protection requirements. Finally, the Commission stated that with the requested actions, licensees may request an amendment to delete the fire protection TS that would now be unnecessary.

The licensees for the Callaway and Wolf Creek plants submitted lead plant proposals to remove fire protection requirements from their TS. This action was an industry effort to obtain NRC guidance on an acceptable format for license amendment requests to remove fire protection requirements from the TS.

Additionally, in the licensing review of new plants, the staff has approved applicant requests to remove fire protection requirements from TS issued with the operating license. Thus, on the basis of the lead-plant proposals and the staff's experience with TS for new licenses, GL 88-12 was issued to provide guidance on removing fire protection requirements from the TS.

3.0 EVALUATION GL 86-10 recommended the removal of fire protection requirements from the TS.

Although a comprehensive Fire Protection Program is essential to plant safety, the basis for this recommendation is that many details of this program that are currently addressed in the TS can be modified without affecting nuclear safety. Such modifications can be made provided that there are suitable administrative controls over these changes. These details, that are presently included in the TS and which are removed by these amendments, do not constitute performance requirements necessary to ensure safe operation of the facility and, therefore, do not warrant being included in the TS. At the same time, suitable administrative controls ensure that there will be careful review and analysis by competent individuals of any changes in the Fire Protection Program, including those technical and administrative requirements removed from the TS to ensure that nuclear safety is not adversely affected.

These controls include: (1) the TS administrative controls that are applicable to the Fire Protection Program; (2) the license condition on implementation of and subsequent changes to the Fire Protection Program; and (3) the 10 CFR 50.59 criteria for evaluating changes to the Fire Protection Program as described in the FSAR.

The proposed changes include the following actions: (1) replace the current license condition 2.C.(3) of the St. Lucie Unit 1 license and add license condition 2.C.(20) to the St. Lucie Unit 2 license with the standard fire protection license condition, (2) remove fire protection requirements from the TS and relocate them to Appendixes 9.5A for both St. Lucie units, and (3) remove the Bases sections relating to fire protection.

Appendixes 9.5A in the UFSARs were created to contain the fire protection requirements currently contained in the TS. Information contained in the TS Bases is now also included in the UFSAR Appendixes 9.5A. No changes have been made to the technical content by this administrative relocation as specified by the requirements of GL 88-12.

Compliance with the fire protection requirements will be assured by maintaining these requirements in appropriate plant procedures and the UFSAR.

These changes offer additional flexibility in updating and maintaining the fire protection program. The proposed changes relocate the requirements from the TS to the UFSARs. Since no technical changes are involved, the relocation of the requirements is administrative in nature.

The staff finds that the incorporation of the Fire Protection Program, and the former TS requirements by reference to the procedures implementing these requirements, into the UFSAR and the use of the standard license condition on fire protection establishes the Fire Protection Program, including the systems, the administrative and technical controls, the organization, and the other plant features associated with fire protection on a consistent status with other plant features described in the UFSAR. Also, the provisions of 10 CFR 50.59 apply directly for subsequent changes the licensee desires to make in the Fire Protection Program. In this context, the determination of the involvement of an unreviewed safety question defined in 10 CFR 50.59(a)(2) will be made based on the "accident .... previously evaluated," being the postulated fire in the fire hazards analysis for the fire area affected by the change. Hence, the proposed license condition establishes an adequate basis for defining the scope of changes to the Fire Protection Program which can be made without prior Commission approval, i.e., without introduction of an unreviewed safety question.

On the basis of its review of the above items, the staff concludes that the licensee has met the guidance of GLs 86-10 and 88-12. Accordingly, the staff finds the proposed changes have no adverse impact on safety and are, therefore, acceptable.

4.0 STATE CONSULTATION

Based upon the written notice of the proposed amendments, the Florida State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. 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 (56 FR 57696). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). 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.

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6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (I) there is reasonable assurance that the 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 Commission's 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 Contributors: F. Rinaldi J. Norris Date: June 11, 1992

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