ML20070U656

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Proposed Tech Specs on Limiting Condition for Operation & Surveillance Requirements Re RCS Operational Leakage & Insps Performed Per Generic Ltr 88-01
ML20070U656
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/01/1991
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20070U651 List:
References
GL-88-01, GL-88-1, NUDOCS 9104090232
Download: ML20070U656 (10)
v • d • e


Text

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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 the requirements of any Technical Specification.

f

/NSERT W l

LA SALLE - UNIT 1 3/4 0-3

REACTOR COOLANT SYSTEM OPERATIONAL LEAXAGE LIMITING CONDITION FOR OPERATION

a. No PRESSURE BOUNDARY LEAKAGE.
b. 5 gpm UNIDENTIFIED LEAKAGE.
c. 25 gpr total leakage averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

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

+-

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
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 with%

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> o,r be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

c. With eny reactor coolant system pressure isolation valve leakage 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. With one or more high/ low pressure interf ace 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 IgggT 'C' alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in a+ least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN va'*in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVE!LLANCE 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 atmospheric particulate and gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
b. Monitoring the primary containment sump flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and-
c. Monitoring the primary containment air coolers condensate flow rate at least once psr 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

LA SALLE - UNIT 1 3/4 4-7 Amendment No.18

4 INSERL A

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, methodt, personnel, and sample expansion inr'uded in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.

INSER1_B

e. 2 gpm increase in UNIDENilf1ED LEAKAGE within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

INSERI.C

e. With any reactor coolant system leakage greater than the limit in e.

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

Et1LL941/9

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 the requirements of any Technical Specification.

A

__A---A i

LA SALLE - UNIT 2 3/4 0-3

4 \

REACTOR COOLANT SYSTEM i

1 OPERATIONAL LEAKAGE-1 LIMITING CONDITION FOR OPERATION ,

i 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b. 5 gpm UNIDENTIFIED LEAKAGE. ,
c. 25 gpm total leakage averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. ,

d' 1 UP" I' ** * '" 't " *

~~NRT 'B' l'"' 'Y'*** P"" ** 1000

- ( _ in Table 3.4.3.2 1.

4 1

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. -

j ACTION:

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

b.

4 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.

With any reartor coolant system pressure isolation valve leakage 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least twe closed valves, or be in at least HOT SHUTDOWN Within the next 12 nours and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,

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 once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local-indication; restore the inoperable ronitor(s) to OPERABLE status within 30 days h,3fg7 r t' or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and-in COLD SHUTOOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS i

4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be l within each of the above limits by a- Monitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i b.

Monitoring 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and the primary containment sump flow rate at least once per

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

LA SALLE - UNIT 2 3/4 4-8 mmen-em-,,,,---mm_,--m,,n n n ws mw n,- , mm-w m es-,; w,,.n y-- --up y - , p m m ., - pr e mc ,g w , ,, ,e--,, -m,,,,.,

INSERLA

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 sample expansion included in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.

IESERLE

e. 2 gpm increase in UNIDENTIFI") LEAKAGF within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

INSERLC

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOHN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l

AiTACHMENT C EVALVA110N OE_SIGNiflCANI_ HAZARDS _ CONSIDERATION I

Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards considerations. According to 10 CFR 50.92 (c), a proposed amendment to an operating license involves no significant hazards considerations if operation of the facility in accordance wl'h the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
3. Involve a significant reduction in a margin of safety.

The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because:

The proposed amendment to the applicability section of the Technical Specifications (paragraph 4.0.5) commits the station to cor. ducting the inservice inspection orogram in accordance with the requirerents of Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff. This revision is administrative in nature and does not affect any accident initiators or initial assumptions used in the plant accident analyses.

Leakage detection systems for the reactor toolant system are provided to alert the operator when leakage rates above normal levels are detected. The proposed amendment to the limiting conditions for operation (LCO) and action requirementi for the reactor coolant system operational leakage limits provides more stringent requirements for detection of unidentified leakage within the primary containment. This additional restriction will enhance the ability for early detection of small flaws in the reactor coolant pressure boundary, thereby, reducing the potential for a significant failure of the pressure boundary. This revision does not adversely affect any of the accident initiators or initial assumptions used in the plant accident analyses.

The proposed changes do not create the possibility of a new or different Lind of accident from any accident previously evaluated because:

The p oposed amendment; do not involve any changes to the facility or the operation of the fattlity as described in the UFSAR. The amendments provide enhantements to the program for early detettlon of pressure boundary leakage and do not create the possibility of any unanalyzed event.

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The proposed changes do not involve a significant reduction in a margin of safety because:

The proposed amendment to paragraph 4.0.5 of the Technical Specifications commits the station to conducting the inservice inspection program in accordance with the requirements of Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff. This revision is purely administrative in nature and has no affect on the margin of safety.

The proposed amendment to the LC0 and action requirements for the reactor coolant system operational leakage limits provides more stringent requirements for detection of unidentified leakage within the primary containment. This additional rest:1ction may help-to enhance the ability for early detection of small flaws in the reactor coolant pressure boundary, thereby, reducing the potential for a significant fail'Jre of the pressure boundary. This proposed amendment will not have an adverse affect on the margin of safety.

The er;!.anced ability for early detection of unidentified leakage may actually increase the margin of safety.

CONCLUSION Guidance has been provided in 51.44 FR 7744 for the application of standards to Itcense change requests for determination of the existence of significant hazards considerations. This document provides examples of amendments which are not likely considered to inv"Ive significant hazards considerations.

This proposed amendment does not involve a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases for the limiting safety system settings or a significant relaxation of the-bases for the limiting conditions for operations. The proposed amendments are administrative in nature or provide greater restrictions, limitations, and controls not included in the present Technical Specifications. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92 (e), the proposed change does not constitute a significant hazards consideration.

I l

turis41/11

. AIIACHMENLD

. E NVI RONM ENIAL AS S E S SME RLSIAIEME RT.E rJ C ADI GIL R EVI LH Commonwealth Edison has evaluated the proposed amendment against the criteria for the identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.20. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided under 10 CFR 51.22(c)(9). This conclusion has been determined because the proposed changes do not pose a significant hazards consideration or do not involve a significant increase in the amounts, and no significant changes in the types, of any effluents that may be released offsite. In addition, the proposed changes provide greater restrictions, limitations, and controls not included in the present Technical Specifications. This request does not involve a significant increase in individual or cumulative occupational radiation ekposure, Therefore, the Environmental Assessment Statement is not applicable for these changes, l

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l F,NLt+8 41/17 I

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