Text

Amends 80 & 64 to Licenses NPF-11 & NPF-18,respectively, Incorporating Changes Into TS to Meet Requirements of Generic Ltr 88-01 Re Intergranular Stress Corrosion Cracking
	ML20079P713
Person / Time
Site:	LaSalle
Issue date:	10/25/1991
From:	Barrett R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20079P716	List: ML20079P713; ML20079P718;
References
	GL-88-01, GL-88-1, NUDOCS 9111130260
	Download: ML20079P713 (14)
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'o, UNITED STATES NUCLEAR REGULATORY COMMISSION n

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COMMONWEALTH EDISON COMPANY.

DOCKET NO. 50-373 LASALLE-COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment. No. 80 -

License Nc. NPF-11 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment filed by the Comonwealth Cdison Company (the licensee) dated April-1, 1991, as supplemented on September 13 and October 17 1991, complies with the standards and

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requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonaity with the application, the provisions of -the Act, and the regulations of the Comissiori; _

C.

There is reasonable assurance:.(i)thattheactivities'authorizedby this amendment can be conducted without endangering the healtn and safety of the_public, and (ii) that such activities will be conducted in compliance with tne Comission's regulations set forth in 10 CFR Chapt::r I; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable retuirements have been satisfied.-

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility: Operating License No. NPF-11 is hereby amended'to read as follows:

9111130260 911025 PDR ADOCK 05000373 P

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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective immediately to be implemented within 30 days after date of issuance.

FOR THE NUCLEAR REGU ATORY COMMISSION eY '

Richard. Barrett, Director Project Directorate III-2 Division c+ Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 25, 1991 I

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ATTACHMENT TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT 3/4 0-3 3/4 0-3 3/3 4-7 3/4 4-7 3/4 4-8 l

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above iriservice inspectica and testing activities shall be in addition to other specified surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification, f.

The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the NRC staff positions on schedule, methods, personnel, and semple expansion included in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC taff.

i LA-SALLE - UNIT 1 3/4 0-3 AMENDMENT NO. 80

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

$ gpm UNIDENTIFIED LEAKAGE.

c.

25 gpm total leakage averaged over any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

d.

1 gpm leakage at a reactor coolant system pressure at 1000 1 50 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1, 2 gpm increase in UNIDENTIFIED LEAKAGE within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

e.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With any reactor coolant system leakage greater than the limits-in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system pressure isolation valve leakage c.

greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed valvos.- or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

With one or more high/ low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less-than the alarm setpoint at least orce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by local indication; restore the inoperable moritor(s) to OPERABLE status within 30 days or be in at least HOT SHUlDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the folloving 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , With any reactor coolant system _ leakage greater than the limit in e, e.

above, identify the source of leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN withia the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS-4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be' within each of the above limits by:

Monitoring the primr.ry containment atmospheric particulate and a.

gaseous radioactivity at least once per 12-hours, LA SALLE - UNIT 1 3/4 4-7 Amendment No. M 80

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.

Monitoring the primary containment sump flow rate on average once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months not to exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,* and c.

Monitoring the primary containment air coolers condensate flow rate at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE:

Pursuant to Specification 4.0.5, except that in lieu of any leakage a.

testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

1.

At least once per 18 months, and 2.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

b.

By demonstrating OPERABILITY of the high/ low pressure interface valve leakage pressure monitors by performance of a:

1.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 2.

CHANNEL CALIBRATION at least once per 18 months, With the alarm setpoint for the:

1.

HPCS system i 100 psig.

2.

LPCS system 5 500 psig.

1 3.

LPCI/ shutdown cooling system 1 400 psig.

4.

RHR shutdown cooling i 190 psig.

5.

RCIC i 90 psig.

Technical Specification 4.0.2 does not apply.

LA SALLE - UNIT 1 3/4 4-8 Amendment No. 2, 10, 80

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NUCLEAR REGULATORY COMMISSION j

WASHING TON, D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASAtt E COUNTY STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE A'nendment No. 64 License No. NPF-18 1.

The Nuclear Regulatory Comistion (the Comission) has found that:

A.

The application for amendment filed by the Comonwealth Edison Company (the licensee) dated April 1,1991, as supplement-d on September 13 and October 17, 1991, complies with the stanF rds and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set fcrth in 10 CFR Chapter 1; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C,

There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and se'",y of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chat er I; t

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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:

l 2

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 64, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the 1

Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective immediately to be implemented within 30 days after date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/

l I

Ric'ard J. Barrett, Director Project Directorate 111-2 Division of Reactor Projects - lii/IV/V Office of Nuclear Reactor Regalation Attachmelit:

Changes to the Technical Specifications Date of Issuance: October 25, 1991

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ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 i

I Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by ar..endment number and r ges identified by contain a vertical line indicating the area of change, a

an asterisk are provided for convenience.

REMOVE INSERT 3/4 0-3 3/4 0-3

+3/4 4-7

3/4 4-7 3/4 4-8 3/4 4-8 3/4 4-9 3/4 4-9

3/4 4-10

3/4 4-10 l

l l

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede tne requiccients of any Technical Specification.

f.

The inservice inspection program for piping identified in NRC Geaeric Letter 88-01 shall be performed in accordance with the NRC staff positions on schedule, methods, personnel, and sample expansion included in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.

LA SALLE - UNIT 2 3/4 0-3 AMENDMENT NO. 64 -

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REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE rEAAAGE DTTECTION sT5TEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

a.

The primary containment atmosphere particulate radioactivity monitoring system, b.

Tne primary containment sump flow monitoring system, and c.

Either the primary containment air coolers condensate flow rate monitoring system or the primary containment atmosphere gaseous radioactivity monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With only two of the above required leakage detection systems OPERABLE, opera-tien may continue for up to 30 days provided grab samples of the containmert atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radioactive monitoring system is inoperable; other-wise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system detection systems shall be demonstrated OPERABLE ty:

Primary containment atmosphere particulate and gaseous monitoring a.

Systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a tHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

b.

Primary containment sump flow monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days ano a CHANNEL CALIBRATION TEST at least once per 18 months.

Primary containment air coolers condensate flow rate monitoring c.

system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a' CHANNEL CALIBRATION at least once per 18 months.

LA SALLE - UNIT 2 3/4 4-7

REACTOR COOLANT SYSTEM i

01 RATIONAL LEAKAGE i

LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

6 gpm UNIDENTIFIED LEAKAGE.

f c.

25 gpm total leakage averaged over any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

d.

I gpm leakage at a reactor coolant system pressure at 1000 1 50 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.

e.

2 ppm incrcase in UNIDENTIFIED LT.AKAGE within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i c.

With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected syster, from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed volves, or be in at least HOT SHUTDOWN within tha next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following i

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

With one or more high/ low pressure interface valve leakage aressure monitors inoperable, restore the inoperable monitor (s) to 0)ERABLE status within 7 days or verify the pressure to be less than the

- alarm setpoint at least once per'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by locai indication;-

restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , e.

With any reactor coolant system leakage greater than the limit in e, above, identify the source of leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a.

Monitoring the primary containment atmospherte particulate and-gaseous radioactivity at least once per 12 houtst LA SALLE-- UNIT 2

'3/4 4-8 Amendment No, 64 w.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.

Monitoring the primary containment sump flow rate on average once pe" 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months not to exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,* and c.

Monitoring the primary containment air :oolers condersate flow rate at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERtBLE:

a.

Pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

1.

At least once per 18 moaths, and 2.

Prior to returning the valve to service follor ng maintenance, d

repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

b.

By demonstrating OPERABILITY of the high/ low pressure interface valve leakage pressure munitors by performance of a:

1.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and 2.

CHANNEL CALIBRATION at least once per 18 months, With the alarm setpoint for the:

1.

HPCS system 5 100 psig.

2.

LPCS system 5 500 psig.

3.

LPCI/ shutdown cooling system 5 400 psig.

4.

RHR shutdown cooling 5 190 psig.

5.

RCIC 5 90 psig.

Technical Specification 4.0.2 does not apply.

LA SALLE - UNIT 2 3/4 4-9 Amendment No. 64

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TABLE 3.4.3.2-1 REACTOR COOLANT SY$ TEM PRESSURE ISOLATION VALVES SY5jg VALVE NUMBER FUNCTION a.

LPCS E21 F006 LPCS Injection E21-F005 LPCS Injection b.

HPCS E22-F005 HPCS Injection E22-F004 HPCS Injection c.

RHR E12-F041A LPCI Injection E12-F041B LPCI Injection E12-F041C LPCI Injection E12-F042A LPCI Injection E12-F042B LPCI Injection E12-F042C LPCI Injection E12-F050A Shutdown Cooling Return E12-F050B Shutdown Cooling Return E12 F053A Shutdown Cooling Return E12 F053B Shutdown Cooling Return E12-F009 Shutdown Cooling Suction E12-F008 Shutdown Cooling Suction d.

RCIC E51-F066 RCIC Head Spray E51-F065 RCIC Head Spray LA SALLE - UNIT 2 3/4 4-10

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ML20079P713

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