ML17228B508

Amends 144 & 84 to Licenses DPR-67 & NPF-16,respectively, Upgrading Existing TS 3/4.4.6.1 for RCS Lds by Adopting STSs for CE Plants to Plant Units

ML17228B508
Person / Time
Site:	Saint Lucie
Issue date:	05/30/1996
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML17228B509	List: ML17228B508 ML17228B510
References
NUDOCS 9606050182
Download: ML17228B508 (16)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER

& LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 144 License No.

DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Florida Power

5. Light Company, et al. (the licensee),

dated November 22,

1995, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.

9606050'l82 9'60530 PDR ADQCK 05000335 P

PDR

2.

3 ~

n 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

'D

(2) to read as follows (2)

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 144, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications'his license amendment is effective as of its date of issuance and shall be implemented within 30 days FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

Frederick J.

Heb'don, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

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.

Remove Pa es 3/4 4-12 3/4 4-13 B3/4 4-4 3/4 4-12 3/4 4-13 B3/4 4-4

3.4.6.1 The following RCS leakage detection systems shall be OPERABLE:

a.

The reactor cavity sump inlet flow monitoring system; and P

b.

One containment atmosphere radioactivity monitor (gaseous or particulate).

MODES 1, 2, 3, and 4.

hQIIQH:

a.

With the required reactor cavity sump inlet flow monitoring system inoperable, perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the sump inlet flow monitoring system to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With all required monitors inoperable, enter LCO 3.0.3 immediately.

d.

The provisions of Specification 3.0.4 are not applicable if at least one of the required monitors is OPERABLE.

4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a.

Performance of the CHANNELCHECK, CHANNELFUNCTIONALTEST, and CHANNELCALIBRATIONof the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.

b.

Performance of the CHANNELCALIBRATIONof the required reactor cavity sump inlet flow monitoring system at least once per 18 months.

ST. LUCIE - UNIT 1 3/4 4-12 Amendment No. 144

DELETED ST. LUCIE - UNIT 1

-" /p 3/4 4-13 Amendment No. ~44

3 (jp C

The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundaty. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973. The LCO is consistent with NUREG-1432, Revision 1, and is satisfied when leakage detection monitors of diverse measurement means are OPERABLE in MODES 1, 2, 3, and 4. Monitoring the reactor cavity sump inlet flow rate, in combination with monitoring the containment particulate or gaseous radioactivity, provides an

'cceptable minimum to assure that unidentified leakage is detected in time to allow actions to place the plant in a safe condition when such leakage indicates possible pressure boundary degradation.

Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM. This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIEDLEAKAGElimitation provides allowance for a limited amount of leakage from known sources whose presence willnot interfere with the detection of UNIDENTIFIEDLEAKAGEby the leakage detection systems.

The total steam generator tube leakage limitof 1 GPM for ail steam generators ensures that the dosage contrib'ution from the tube leakage willbe limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents.

PRESSURE BOUNDARYLEAKAGEof any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Therefore, the presence of any PRESSURE BOUNDARYLEAKAGErequires the unit to be promptly placed in COLD SHUTDOWN.

The Surveillance Requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.

IJ The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduce the potential for Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are ST. LUCIE-UNIT1 B 3/4 4-4 Amendment No i44

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER 5 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.

84 License No.

NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:

A.

C.

D.

E.

The application for amendment by Florida Power

& Light Company, et al.

(the licensee),

dated November 22,

1995, complies with the standar'ds 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; a

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; 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 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.

3.

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 S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. B4, are hereby incorporated in the

'icense.

The licensee shall'operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications F

Date of Issuance:

May 30, 1996 Frederick J.

HebUon, Director Project Directorate II-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

3.4.6.1 The following RCS leakage detection systems shall be OPERABLE:

a.

The reactor cavity sump inlet flow monitoring system; and W

b.

One containment atmosphere radioactivity monitor (gaseous or particulate).

MODES 1, 2, 3, and 4.

hQILQH:

a.

With the required reactor cavity sump inlet flow monitoring system inoperable, perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the sump inlet flow monitoring system to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With all required monitors inoperable, enter LCO 3.0.3 immediately.

d.

The provisions of Specification 3.0.4 are not applicable if at least one of the required monitors is OPERABLE.

4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a.

Performance of the CHANNELCHECK, CHANNELFUNCTIONALTEST, and CHANNELCALIBRATIONof the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.

b.

Performance of the CHANNELCALIBRATIONof the required reactor cavity sump inlet flow monitoring system at least once per 18 months.

ST. LUCIE - UNIT2 3/4 4-18 Amendment No. 84

IJ

Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems,"

May 1973. The LCO is consistent with NUREG-1432, Revision 1, and is satisfied when leakage detection monitors of diverse measurement means are OPERABLE in MODES 1, 2, 3, and 4.

Monitoring the reactor cavity sump inlet flow rate, in combination with monitoring the containment particulate or gaseous radioactivity, provides an acceptable minimum to assure that unidentified leakage is detected in time to allow actions to place the plant in a safe condition when such leakage indicates possible pressure boundary degradation.

Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm. This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 gpm IDENTIFIEDLEAKAGElimitation provides allowances for a limited amount of leakage from known sources whose presence willnot interfere with the detection of UNIDENTIFIEDLEAKAGEby the leakage detection systems.

The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is IDENTIFIEDLEAKAGE and willbe considered as a portion of the allowable limit.

The total steam generator tube leakage limitof 1 gpm for all steam generators ensures that

. the dosage contribution from the tube leakage willbe limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 gpm limitis consistent with the assumptions used in the analysis of these accidents.

The 0.5 gpm leakage limitper steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.

PRESSURE BOUNDARYLEAKAGEof any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Therefore, the presence of any PRESSURE BOUNDARYLEAKAGErequires the unit to be promptly placed in COLD SHUTDOWN.

The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining ST. LUCIE-UNIT2 B 3/4 4-5 Amendment No. 8

ATTACHMENT TO LICENSE AMENDMENT NO. 8 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.

3/4 4-18 B3/4 4-5 Insert Pa es 3/4 4-18 3/4 4-5