Text

License Amendment Request, Standardization of Administrative Controls - Responsibility and Organization
	ML13219A840
Person / Time
Site:	Saint Lucie
Issue date:	07/26/2013
From:	Jensen J; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2013-190
	Download: ML13219A840 (37)
	v • d • e

0July 26, 2013 L-2013-190 FPL. 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 St. Lucie Plant Units 1 and 2 Docket Nos. 50-335 and 50-389 Re: License Amendment Request Standardization of Administrative Controls - Responsibility and Organization Pursuant to 10 CFR 50.90, Florida Power & Light Company (FPL) hereby requests to amend Renewed Facility Operating Licenses DPR-67 for St. Lucie Unit 1 and NPF-16 for St. Lucie Unit 2. These proposed license amendment requests (LARs) align St.

Lucie Technical Specifications with NUREG-1432, Revision 4, Combustion Engineering Plants Standard Technical Specifications language describing the Administrative Controls requirements for Responsibility and Organization.

Please process these LARs within one (1) year of receipt, and once approved, the amendments will be implemented within 90 days. There are no regulatory commitments made in this submittal.

These changes have been reviewed by the St. Lucie Plant Onsite Review Group.

Pursuant 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.

Should you have any questions regarding this submittal, please contact Mr. Eric Katzman, Licensing Manager at (772) 467-7734.

I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.

Executed on Z-V0 Very truly urs, Sit V* e ,ident

"-----4*"Cie Plant Enclosure cc: Ms. Cynthia Becker Chief - Florida Bureau of Radiation Control Florida Power & Light Company (Doi~1 6501 S. Ocean Drive, Jensen Beach, FL 34957 KG(_

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 1 of 36 Enclosure Evaluation of Proposed Changes Standardization of Administrative Controls - Responsibility and Organization

1.

SUMMARY

DESCRIPTION

2. DETAILED DESCRIPTION

3. TECHNICAL EVALUATION

4. REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration Determination 4.3 Conclusions

5. ENVIROMENTAL CONDISERATION

6. REFERENCES ATTACHMENTS

1. St. Lucie Unit 1 Technical Specifications Page Markups

2. St. Lucie Unit 2 Technical Specifications Page Markups

3. St. Lucie Unit 1 Technical Specifications Retyped Pages

4. St. Lucie Unit 2 Technical Specifications Retyped Pages

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 2 of 36

1.

SUMMARY

DESCRIPTION Pursuant to 10 CFR 50.90, Florida Power & Light Company (FPL) requests to amend Renewed Facility Operating License DPR-67 for St. Lucie Unit 1 and NPF-16 for St. Lucie Unit 2. These proposed license amendment requests (LARs) align St. Lucie Technical Specifications (TS) with NUREG-1432, Revision 4, Combustion Engineering Plants Standard Technical Specifications (STS) describing the Administrative Controls requirements for the Responsibility and Organization, which includes Onsite and Offsite Organizations and the Unit Staff.

The proposed amendment will revise TS 6.1, Responsibility and 6.2, Organization to be consistent with STS 5.1 Responsibility and 5.2 Organization, which directly reference the requirements in 10 CFR 50.54(m). The current St. Lucie Units 1 and 2 TS 6.1 and 6.2 use custom language to define the requirements of the regulation.

2. DETAILED DESCRIPTION The proposed amendments will revise TS 6.1 and 6.2 which use custom language to enforce the requirements of 10 CFR 50.54(m) to be consistent with. STS 5.1 and 5.2 language.

For St. Lucie Unit 1, INDEX, Section 6.2.3 is deleted (page XIV).

" For St. Lucie Unit 2, INDEX, Section 6.2.3 and Table 6.2-1 are deleted (pages XVIII and XXV, respectively).

" TS 6.1 will be revised to delete the current step 6.1.2 and add new step 6.1.2 as follows:

6.1.2 The Shift Supervisor shall be respursible for the control room command function.

During any absence of the Shift Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while both units are in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

TS 6.2.2, TS Table 6.2-1 and TS 6.2.3 are deleted and replaced with new TS 6.2.2, which contains language consistent with STS 5.2.2 as follows:

6.2.2 The unit staff organization shall meet the requirements of 10 CFR 50.54(m) and include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. A minimum of three non-licensed operators is required when both units are in MODES 5 or 6.

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 3 of 36

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 6.2.2.a and 6.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. A health physics technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. The operations manager or assistant operations manager shall hold an SRO license.

e. An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA may be an STA qualified Shift Supervisor or a dedicated STA. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

3. TECHNICAL EVALUATION The revisions to TS 6.1, 6.2 and Table 6.2-1 have no technical implications with respect to the station organization, responsibilities, or unit staffing requirements. The changes do not affect the minimum shift complement in any mode of operation. The current TS use custom language to meet the intent of 10 CFR 50.54(m).

The changes to the INDEX are editorial in that they are conforming changes that reflect the proposed deletion of TS 6.2.3 and TS Table 6.2-1.

The current TS 6.1.2 contains two distinct statements.

The first sentence related to the control room command function is redundant to the revised TS 6.1.2 (Insert 1), and therefore is not required. The revised TS 6.1.2 is consistent with STS 5.1.2 and the current TS Table 6.2-1 requirements. The St. Lucie Unit 1 and 2 TS currently include this requirement in TS Table 6.2-1.

The second sentence concerning a management directive related to responsibility for the plant is an administrative requirement. Proposed TS 6.1.2 assigns responsibility for the control room command function. The requirement to issue a management directive is redundant to the TS requirement and therefore, is unnecessary.

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 4 of 36 TS 6.2.2, Table 6.2-1, and TS 6.2.3 are deleted and replaced with new TS 6.2.2.

These current TSs meet the intent of 10 CFR 50.54(m) using customized language, however, having separate TS for each unit related to site shift complement requirements introduces unintended conservatisms that are not necessary to meet the regulation. The current TS for each unit imply that the second reactor operator for the operating unit be in the control room which is more conservative that the 10 CFR 50.54(m) requirements. The revised TS are consistent with STS 5.2.2 and will more clearly identify the requirements necessary to ensure compliance with 10 CFR 50.54(m).

Because the proposed changes are consistent with the STS, they are administrative in nature and have no technical implications. The TS will continue to ensure compliance with the regulation. Therefore, nuclear safety is maintained.

4. REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria Common to St. Lucie Units 1 and 2 10 CFR 50.36 Technical Specifications Specifically, 10 CFR 50.36(c) identifies the categories of information to be included in the TS.

10 CFR 50.54 Conditions of License Specifically 10 CFR 50.54(m) is applicable to St. Lucie Units 1 and 2, and establishes the staffing requirements for and duties of licensed operators.

The proposed changes to the Technical Specifications (TS) are not contrary to the cited regulatory criteria; rather the requirements are enforced by providing a direct reference to the regulation within the TS language. Furthermore, the TS that will remain are consistent with the language in NUREG-1432, Revision 4, Combustion Engineering Plants Standard Technical Specifications, which has previously been approved by the Nuclear Regulatory Commission. As such, the ability to comply with the regulatory criteria is enhanced by the changes.

4.2 No Si-gnificant Hazards Consideration Determination FPL is requesting approval of changes to St. Lucie Units 1 and 2 TS related to station organization, responsibilities and operators staffing requirements. The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission's regulation 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the amendment would not result in any one of the following consequences:

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 5 of 36 (1) Involve a significant increase in the probability or consequences of an accident previously evaluated, (2) Create the possibility of a new or different kind of accident from any accident previously evaluated, (3) Involve a significant reduction in a margin of safety.

As required by 10 CFR 50.91(a), an analysis of the issue of no significant hazards consideration is presented below:

(1) Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed changes are administrative in nature and will not result in any significant increase in the probability of consequences of an accident as previously evaluated, as the proposed TS changes are consistent with the NUREG-1432, Combustion Engineering Plant Standard Technical Specifications. Further, the proposed changes do not introduce additional risk or greater potential for consequences of an accident that has not previously been evaluated. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

(2) Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

No. The proposed changes are administrative in nature and do not involve a physical modification of the plant. No new or different type of equipment will be installed. The proposed changes will not introduce new failure modes/effects that could lead to an accident for which consequences exceed that of accidents previously analyzed.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

(3) Does the proposed change involve a significant reduction in a margin of safety?

No. The proposed changes will not involve a significant reduction in a margin of safety in that the changes are administrative in nature. No plant equipment or accident analyses will be affected. Additionally, the proposed changes will not relax any criteria used to establish safety limits, safety system settings, or the bases for any limiting conditions for operation. Safety analysis acceptance criteria are not affected. Plant operation will continue within the design basis. The proposed changes do not adversely affect systems that respond to safely shutdown the plant, and maintain the plant in a safe shutdown condition. Consequently, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above evaluation, it is concluded that the proposed amendments do not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(b), and, accordingly, a finding of "no significant hazards consideration" is justified.

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 6 of 36 4.3 Conclusion Based on the considerations described above, (1) 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 in compliance with the Commission's regulations, and (3) the issuance of amendments will not be inimical to the common defense and security or to the health and safety of the public.

5. ENVIRONMENTAL CONSIDERATION The proposed amendments concerning administrative changes relating to the station organization, responsibilities and unit staffing have been evaluated as not involving a significant hazards consideration. Consequently, the proposed amendments satisfy categorical exclusion criterion 10 CFR 51.22(c)(10)(ii); changes to recordkeeping, reporting, or administrative procedures or requirements. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendments.

6. REFERENCES

1. St. Lucie Unit 1 Technical Specifications

2. St. Lucie Unit 2 Technical Specifications

3. NUREG-1432, Revision 4.0, Combustion Engineering Plant Standard Technical Specifications, Volume 1

4. Code of Federal Regulations, Title 10, Energy

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 7 of 36 Attachment 1 Attachment I St. Lucie Unit I Technical Specifications Marked Up Pages This coversheet plus 7 pages.

INDEX page XIV TS page 6-1 Insert 1 TS page 6-2 Insert 2 TS page 6-4 TS page 6-5

INDEX ADMINISTRATIVE CONTIROLS SECTION PAGE 6.1 RESPONSIBILITY ........................................................................................................ 6 -1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATION ................................................................... 6-1 6.2.2 UNIT STAFF ................................................................................................................. 6-2 6.2.3... .. .......................... ............................................................. 65 6.3 UNIT STAFF QUALIFICATIONS .................................................................................. 6-6 6.4 DELETED 6.5 DELETED ST. LUCIE - UNIT 1 XlV Amendment No. 69, 03, 434, 489, 4-99,

a n1 Arl 1KIIQTDATI1k/= 1-flMTDr1I Q 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 Super.'-isor, or during his absence from the control room a designated individual, shall be rcspensible fer the eentrcl racm ccmmand funcetien.

Add INSERT I A Fmanagement dircctive te thus effeet, signed by the efrperate effieer with diroc-t (ne pae)roponibilitY t for the plant, shall be rcissued to all statien perzecnncl en an an~nual bases.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 An onsite and an offsite organization shall be established 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 Quality Assurance Topical Report and updated in accordance with 10 CFR 50.54(a)(3).

The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the UIFSAR or the Quality Assurance Topical Report.

b. A specified corporate officer 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 safe operation and shall have control over those onsite 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 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 radiation protection 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 isjeopardized or in the event of unnecessary personnel radiation exposures.

ST. LUCIE - UNIT 1 6-1 Amendment No. -15,69, 99, 4O,074265, 4465, 47,4.499,.26B

INSERT 1 6.1.2 The Shift Supervisor shall be responsible for the control room command function.

During any absence of the Shift Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while both units are in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

r. n ADlMINIS5TRATIVE COfNTPflI 6.2 ORGANIZATION (continued)

UNIT STAFF Each on duty shift shall be composed of at least the minimum shift c sition shown in Table 6.2-1.

b. Deleted.

c. A health physics tecnca st hnfuel is in the reactor.

(next page)I f Ii flL I Ile IMaIL! I P1 1Yb1L;5 RILA 11IlUldl I n lay De NeSS Man Me 11 V not to "xco^d 2 he'"9, in ordeo t- acco-modate unexpooted absenee, provided immeda action is taken to fill the F..u...d positions.

ST. LUCIE - UNIT 1 6-2 Amendment No. 40, 2-5, 55, 69, 92, 44, 4-469, 47-7-, 4-99

INSERT 2 6.2.2 The unit staff organization shall meet the requirements of 10 CFR 50.54(m) and include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. A minimum of three non-licensed operators is required when both units are in MODES 5 or 6.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 6.2.2.a and 6.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. A health physics technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. The operations manager or assistant operations manager shall hold an SRO license.

e. An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA may be an STA qualified Shift Supervisor or a dedicated STA. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

I 'ILn D.Z-I MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH TWO SEPARATE CONTROL ROOMS WITH UNIT 2 IN MODE 5 OR 6 OR DEFUELED SITION NUMBER OF INDIVIDUALS REQUIRED TO FILL PO/ITION MODE 1, 2, 3 or 4 MODE 5dr 6 SS( 0) 1a 1 SRO 1 one RO 2 1 AO 2 STA I / None WITH UNIT21NMODE1,2,3,o4 POSITION UMBER OF INDIVIDUALS RE!?bIRED TO FILL POSITION

\MODE 1, 2, 3 or4 MODE 5 or 6 SS (SRO) Ia SRO None RO 1 AO STA

None SS - Shift Supervisor with a Senior tor Operator's License on Unit 1 SRO - Individual with a Senior Reac r Op rator's License on Unit 1 STA - Shift Technical Advisor RO - Individual with a Reactor perator's Li rnse on Unit 1 AC - Auxiliary Operator xcept for the Shift Supervisor, t Shift Crew Compositi may be one less than the minimum requirement f Table 6.2-1 for a period time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommo te unexpected absence of on- uty shift crew members provided immedi action is taken to restore the Shift Crew Composi-tion to within the minimu equirements of Table 6.2-1. This pro ision does not permit any shift cre position to be unmanned upon shift chan due to an oncoming shift crewm being late or absent.

During any absen of the Shift Supervisor from the Control Room while e unit is in MODE 1, 2 , or 4, an individual (other than the Shift Technical Advis with a valid S license shall be designated to assume the Control Room c mand function. Du ng any absence of the Shift Supervisor from the Control Room while the u it is in MODE 5 or 6, an individual with a valid SRO or RO license shall be signated to assume the Control Room command function.

a/ In vidual may fill the same position on Unit 2.

b/ ne of the two required individuals may fill the same position on Unit 2.

If STA position is filled by an STA qualified Shift Supervisor or dedicated STA, then th individual may fill the same position on Unit 2.

A single, onsite STA position shall be manned in Mode 1, 2, 3, and 4 unless the Shift Supervisor meets the qualifications for the STA as required by Technical Specification 6.3.1 an individual on each unit with a Senior Reactor Operator's license meets the qualifications fo S U-UT .

Th A.., 1 TmentNo. Spec-ficaton 6,,,Amend 6.3.1.

ST. LUCIE - UNIT 1 6-4 Amendment No. 3-7-, ,541, 6-2,69,4-174,

-'-7l--

6.O0.LI .A1 .ITRATIV/'I ONTRe,,

f. DELETED

g. The operationGszuporiseF she"l held a geniorF Reaetfr Opefotfr Iieense.

SHIFT TECHNICAL ADOVISOR FUI NIlTION 6.2.3 An didulshall provide adviseoy teehnwcal suppeot to the unit operationc shift crcW i the areas of thecfmaI hydraulies, reetact --- in---ring, and plant analysis with rogard to the safe operation of the unit. This individu al ;.hall meet the qualificatiens speeified by the Commission Policy Statement en FEnginooring Expeotise on Ghift.

"',,-.ED .

ST. LUCIE - UNIT 1 6-5 Amendment No. 69, 93, 44-5, 1-26, 456, 4-85 4-99,-2e&

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 15 of 36 Attachment 2 Attachment 2 St. Lucie Unit 2 Technical Specifications Marked Up Pages This coversheet plus 8 pages.

INDEX page XVIII INDEX page XXV TS page 6-1 Insert 1 TS page 6-2 Insert 2 TS page 6-5 TS page 6-6

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPO NSIBILITY ....................................................................................................... 6-1 6.2 O RGANIZATIO N ........................................................................................................... 6-1 6.2.1 O NSITE AND O FFSITE O RGANIZA TIO N ................................................................... 6-1 6.2.2 UNIT STAFF ................................................................................................................. 6-2 6.2.3 "1 I-I IIFllT..IP -6L ABVISE)R I IJ I IUI*I .................................................................

6.3 UNIT STAFF Q UALIFICATIO NS .................................................................................. 6-6 6.4 DELETED ..................................................................................................................... 6-7 6.5 DELETED ..................................................................................................................... 6-7 ST. LUCIE - UNIT 2 XVilI Amendment No. 2-9, 7- 8, 4-, 446, 16 INDEX LIST OF TABLES (Continued)

TABLE PAGE 3.7-1 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION W ITH BOTH STEAM GENERATORS ...................................................... 3/4 7-2 3.7-2 STEAM LINE SAFETY VALVES PER LOOP .................................................... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND A NA LY S IS PRO G RA M...................................................................................... 3/4 7-8 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL ................................................ 3/4 7-22 3.7-3a D E LET E D ........................................................................................................ 3/4 7-26 3.7-3b D E LET E D ........................................................................................................ 3/4 7-27 3.7-4 DELETED 3.7-5 DELETED 4.8-1 DIESEL GENERATOR TEST SCHEDULE ........................................................ 3/4 8-8 4.8-2 BATTERY SURVEILLANCE REQUIREMENT ................................................ 3/4 8-12 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BY PA S S D EV IC ES .......................................................................................... 3/4 8-18 4.11-1 DELETED 4.11-2 DELETED 3.12-1 DELETED 3.12-2 DELETED 4.12-1 DELETED 5.6-1 MINIMUM BURNUP COEFFICIENTS ................................................................... 5-4o > ¢<

5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS ................................................... 5-5 6.2-1 MINIMUM SI lIFT CREW C1OMPV. SITIlVN TWOl UNITS WITVI I TIWO SEPARATE CO,NTR*OR I.I L R OM .................................................................... 6.

ST. LUCIE - UNIT 2 XXV Amendment No. . 4. 5. 68 74, 44-7, 6ý&

an AnRA1Ki1QTDAT1X/= ff)K1TPf)1 Q 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 Sh.ft Suporvior, or during hi- abs., .. f.. ,. he cont roI room, a designated shal b i I 1 Mndividual, sible fir the eentril room i ommand funition. A Addx INSeRT) managemgent directive to this effect, signed by the corporate afficer with direet page).responsibility f.r the plant, shall be reissued to all statiln person.el eI an anIuaI 6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 An onsite and an offsite organization shall be established 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 Quality Assurance Topical Report-and updated in accordance with 10 CFR 50.54(a)(3).

The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the UFSAR or the Quality Assurance Topical Report.

b. A specified corporate officer 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 those onsite 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 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 radiation protection 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. 4-3 2-9. 45.

47, 695, 85, 4-24, 446, 4GQ

INSERT 1 6.1.2 The Shift Supervisor shall be responsible for the control room command function.

During any absence of the Shift Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while both units are in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

6.0 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF

a. Each on duty shift shall be composed of at least the minimum shift w composition shown in Table 6.2-1.

b. DETED

c. A health sics technician# shall be on site when el is in the reactor.

d. Either a license 0 or licensed SRO lim'd to fuel handling who has no concurrent responsib es during this o ration shall be present during fuel handling and shall direct upervis I CORE ALTERATIONS.

e. DELETED f.DEEE

g. The operation upervisor shall hold a Senior ctor Operator License.

Thealth physics technician may be less than the minimum requirement for a period o ie not o exeed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate actio is

/ *ko* o .fi'l the req,-ired positions.

Add INSERT 2 (next page)

ST. LUCIE - UNIT 2 6-2 Amendment No. 2-, 65,65,93, 4a, 4465, 166

INSERT 2 6.2.2 The unit staff organization shall meet the requirements of 10 CFR 50.54(m) and include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. A minimum of three non-licensed operators is required when both units are in MODES 5 or 6.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 6.2.2.a and 6.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. A health physics technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. The operations manager or assistant operations manager shall hold an SRO license.

e. An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA may be an STA qualified Shift Supervisor or a dedicated STA. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

i I*tDE: 0.2- 1 MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH TWO SEPARATE CONTROL ROOMS WITH UNIT 1 IN MODE 5 OR 6 OR DEFUELED /

P' SITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POTION MODE 1, 2, 3, or 4 MODE 5 6 SS( 0) Ia la SRO 1 ne RO 2 1 AO 2 STA* 1 None WITH UNIT 1 IN MODE 1, 2,3 ory POSITION "*NUMBER OF INDIVIDUALS REQ/URED TO FILL POSITION

\MODE 1, 2, 3, or 4 MODE 5 or 6 SS (SRO) 1a SRO None RO 1 AO 1 STA

None SS - Shift Supervisor with a Senior R tor Operator's License on Unit 2 SRO - Individual with a Senior Reactor 60\erator's License on Unit 2 RO - Individual with a Reactor Oper .or'sicense on Unit 2 AO - Auxiliary Operator STA - Shift Technical Advisor HDELETED Except for the Shift Supervisor, the ,ift Crew Composit!n may be one less than the minimum requirements oy able 6.2-1 for a periodf time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acco modate unexpected abserne of on-duty shift crew members provided imme late action is taken to restore e Shift Crew Composition to within the mi mum requirements of Table 6.2-1. This provision does not permit any shift c w position to be unmanned upon shi change due to an oncoming shift cre an being late or absent.

During any absence the Shift Supervisor from the Control Room whi the unit is in MODE 1, 3 or 4, an individual (other than the Shift Technical Advisor) with a v d SRO license shall be designated to assume the Cont I Room comman function. During any absence of the Shift Supervisor from e Control Room hile the unit is in MODE 5 or 6, an individual with a valid SRO or RO licen shall be designated to assume the Control Room command functi n.

a/ lndiv ual may fill the same position on Unit 1.

b/ 0 of the two required individuals may fill the same position on Unit 1.

c/ STA position is filled by an STA qualified Shift Supervisor or dedicated STA, then t individual may fill the same position on Unit 1.

A single, onsite STA position shall be manned in Mode 1, 2, 3, and 4 unless the Shift Supervisor meets the qualifications for the STA as required by Technical Specification 6.3. or an individual on each unit with a Senior Reactor Operator's license meets the qualifications Uo,I I

,dL . . I .

t hI e T A aOs I r* e .~ uil e b-y I e cl nIII e, l S p e I cifi .c a 6 3 ST. LUCIE - UNIT 2 6-5 Amendment No. 44,3

6.0 ADMINISTRATIVE CONTROLS 6.2.3 H8IFT TE-CH'NICAL ADVISOR FUN'CTIN An individual shall provide edvisery tochnieal suppeot to the unit eperatiens shift crow in the aroa6 9f thormfal hydraulies, rcacter cngincoring@, and plant an~al;i With rF.gard te thec safe opefratiein cf the unit. This in.*iidual shall meet the.ualificaticns sp..ifi'd by the Commiion Policy StAtcmcnt on Eni"neerig Expe*tise on Shift.

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI /

ANS-3.1-1978 for comparable positions, except for:

(1) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor who shall have specific training in plant design and plant operating characteristics, including transients and accidents, and any of the following educational requirements:

- Bachelor's degree in engineering from an accredited institution; or

- Professional Engineer's (PE) license obtained by successful completion of the PE examination; or

- Bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mathematical, or engineering sciences, or

- Bachelor's degree in physical science from an accredited institution, including course work in the physical, mathematical, or engineering sciences.

(3) the Multi-Discipline Supervisors who shall meet or exceed the following requirements:

a. Education: Minimum of a high school diploma or equivalent.

b. Experience: Minimum of four years of related technical experience, which shall include three years power plant experience of which one year is at a nuclear power plant.

c. Training: Complete the Multi-Discipline Supervisor training program.

6.3.2 For the purpose of 10 CFR 55.4, a licensed senior reactor operator and a licensed reactor operator are those individuals who, in addition to meeting the requirements of 6.3.1, perform the functions described in 10 CFR 50.54(m).

ST. LUCIE - UNIT 2 6-6 Amendment No. 5. 49. 65. 69. 402. 143.

4469, 4

St. Lucie Units 1 and 2 L-2013-190 Docket Nos. 50-335 and 50-389 Enclosure License Amendment Request Page 24 of 36 Attachment 3 Attachment 3 St. Lucie Unit 1 Technical Specifications Retyped Pages This coversheet plus 5 pages.

INDEX page XIV TS page 6-1 TS page 6-2 TS page 6-4 TS page 6-5

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6 .1 R E S P O NS IBILIT Y ........................................................................................................ 6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATION ................................................................... 6-1 6 .2 .2 UNIT S T AF F ................................................................................................................. 6 -2 6.3 UN IT STA FF Q UA LIFICATIO NS .................................................................................. 6-6 6.4 DELETED 6.5 DELETED ST. LUCIE - UNIT 1 XlV Amendment No. 69, 93, 434, 489, 499, 240

6.0 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 shall be responsible for the control room command function.