Text

Amends 87 & 53 to Licenses NPF-14 & NPF-22,respectively. Amends Revise Tech Spec Action Statement for Drywell Floor Drain Sump Flowrate Monitoring Sys
	ML17156B145
Person / Time
Site:	Susquehanna
Issue date:	05/04/1989
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17156B146	List: ML17156B145; ML17156B147;
References
	NUDOCS 8905190272
	Download: ML17156B145 (18)
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~O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 PENNSYLVANIA POWER

& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.

DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. NPF-14 1.

The Nuclear Regulatory CoIImIission (the ComIission or the NRC) having found that; A.

The application for the amendment filed by the Pennsylvania Power Light Company, dated November 9, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the CoIImIission's 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 regulations of the Comission; 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 fn compliance with the CoIImIission's regulations set forth in 10 CFR Chapter 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 Cennission'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 attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

87 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8905i90272 890504 PDR ADOCK 05000387 PDC

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This license amendment, is effective as of its date of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 4, 1989

/s/

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II A

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This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

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ATTACHMENT TO LICENSE AMENDMENT NO.

87 FACILITY OPERATINA LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The overleaf pages are provided to maintain document completeness.*

REMOVE 3/4 4-5*

3/4 4-6 3/4 4-7*

3/4 4-8 INSERT 3/4 4-5*

3/4 4-6 3/4 4-7*

3/4 4-8

'REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY/RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of at least 10 of the following reactor coolant system safety/relief valves shall be OPERABLE with the specified code safety valve functian lift settings:" ""

2 safety-relief valves 8 1146 psig

+1%

4 safety-relief valves 8 1175 psig +lX 4

safety-relief valves ja 1185 psig +lX 3

safety-relief valves 8 1195 psig +IX 3

safety-relief valves 0 1205 psig

+1%

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With the safety va'Ive function of one or more of the abave required safety/relief valves inoperable, 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 COLO SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With ane or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 1054F, close the stuck open relief valve(s); if unable to clase the open valve(s) within 2 minutes ar if suppression pool water temperature is 1054F ar greater, place the reactor mode switch in the Shutdown position.

c.

With one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 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 COLO SHUTDOWN within the fallowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREMENTS 4.4.2 The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE with the setpoint verified to be 0. 25 of the full open noise level by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a

b.

Calibration in accordance with procedures prepared in conjunction with its manufacturer's recommendatians at least once per 18 months.

e 1 t setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

""Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling.

Ache provisions of Specification 4. 0. 4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

SUSQUEHANNA - UNIT 1 3/4 4-5 Amendment No.36

REACTOR COOLANT SYSTEM 3/4. 4. 3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS r

LIMITING CONDITION FOR OPERATION 3.4.3.1 At least the following reactor coolant system leakage detection systems shall be OPERABLE:

a.

Two drywell floor drain sump level channels, and b.

One primary containment atmosphere gaseous radioactivity monitoring system channel and one containment atmosphere particulate radio-activity monitoring system channel aligned to the drywell.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

'a ~

b.

With one or both channels of the drywell floor drain sump level monitoring system inoperable, 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 both channels of the gaseous radioactivity monitoring system inoperable or with both channels of the particulate radioactivity monitoring system inoperable, operation may continue for up to 30 days provided grab samples of the containment 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 .

If at least one channel of the affected monitoring system cannot be returned to OPERABLE status and aligned to the drywell within 30 days, or the grab samples are not obtained and analyzed as required, 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 RE UIREMENTS 4.4.3. 1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:

a.

Primary containment atmosphere particulate and gaseous monitoring 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

CHANNEL FUNCTIONAL TEST at least once per 31 days and a

CHANNEL CALIBRATION at least once per 18 months.

b.

Drywell floor drain sump level monitoring system"performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

SUS(UEHANNA - UNIT 1 3/4 4-6 Amendment No. 87

'REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 a ~

b.

C.

d.

e.

Reactor coolant, system leakage sha11 be limited to:

No PRESSURE BOUNDARY LEAKAGE.

5 gpm UNIDENTIFIED LEAKAGE.

25 gpm total leakage averaged over any 24-hour period.

1 gpm leakage at a reactor coolant system pressure of 1000 i 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2"l.

2 gpm increase in UNIDENTIFIED LEAKAGE within any 4-hour period.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a4 b.

C.

d.

e.

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 ; 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 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 one closed manual or deactivated automatic valves, 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 one or more of the high/low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1 inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm pressure at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 4-hour period, identify the source of leakage increase as not service sensitive Type 304 or 316 austenitic stainless steel 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 COLO SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SUSQUEHANNA - UNIT 1 3'-7 Amendment No. 36

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and b.

Monitoring the drywell floor drain sump level at least once per 4

hours.'.

Oetermining the total IDENTIFIEO LEAKAGE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a 0 b.

At least once per 18 months, and 0

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 CONOITION 3.

4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with the alarm setpoints per Table 3. 4. 3. 2-1 by performance of a:

a.

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

CHANNEL CALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 1 3/4 4"8 Amendment No. 87

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 PENNSYLVANIA POWER

& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.

DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. NPF-22 I.

The Nuclear Regulatory ComIission (the Comaissfon or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power Light Company, dated November 9, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended

<the Act),

and the ComIission's regulations set forth in 10 CFR Chapter I; 8.

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:

(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 ComIfssion's regulations set forth in 10 CFR Chapter I; 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 5l of the COIImIission'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 attachment to this license amendment and paragraph 2.C.(2) of, the Facility Operating License Ho. NPF-22 is hereby amended to read as follows:

(2)

Technical S eciffcations and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

53 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.

PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 4, yg89

/s/

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II g't i n 89 PDI-2/PM MThadani:tr P//fan 89 OGC

/89 PDI-2/D QWutler q ~//89

I4 44'I 4I 4'4 4;li I' 4="> "

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4

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

ga> 4, y9Bg Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

ATTACHMENT TO LICENSE AMENDMENT NO.

53 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following"pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The overleaf pages are provided to maintain document completeness.*

RENOVE 3/4 4-5*

3/4 4-6 3/4 4-7*

3/4 4-8 INSERT 3/4 4-5*

3/4 4-6 3/4 4-7*

3/4 4-8

REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY/RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of at least 10 of the following reactor coolant system safety/relief valves shall be OPERABLE with the specified code safety valve function lift settings:" ""

2 safety-relief valves 8 1146 psig +IX 4

safety-relief valves 8 1175 psig +i%

4 safety-relief valves 9 1185 psig +IX 3

safety-relief valves 9 1195 psig +IX 3

safety-relief valves 0 1205 psig +lX APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

b.

C.

With the safety valve function of one or more of the above required safety/relief valves inoperable, 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 COLO SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With one or more safety/relief valves stuck open, provided that sup-pression pool average water temperature is less than 1054F, close the stuck open relief valve(s); if unable to close the open valve(s) within 2 minutes or if suppression pool water temperatQre is 105'F or greater, place the reactor mode switch in the Shutdown position.

With one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREMENTS 4.4.2 The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE with the setpoint verified to be 0.25 of the full open noise levels'by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a

b.

Calibration in accordance with procedures prepared in conjunction with its manufacturer's recommendations at least once per 1S months.ft "The liftsetting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

"Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling.

SInitial setting shall be in accordance with the manufacturer's recommendation.

Adjustment to the valve full open noise level shall be accomplished during the startup test program.

%The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

SUS)UEHANNA - UNIT 2 3/4 4-5

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION C

j

~

3.4.3.1 At least the following reactor coolant system leakage detection systems shall be OPERABLE:

a.

Two drywell floor drain sump level channels, and b.

One primary containment atmosphere gaseous radioactivity monitoring system channel and one containment atmosphere particulate radioactivity monitoring system channel aligned to the drywell.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a ~

b.

With one or both channels of the drywell floor drain sump level monitoring system inoperable, 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 both channels of the gaseous radioactivity monitoring system inoperable or with both channels of the particulate radioactivity monitoring system inoperable, operation may continue for up to 30 days provided grab samples of the containment 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 .

If at least one channel of the affected monitoring system cannot be returned to OPERABLE status and aligned to the drywell within 30 days, or the grab samples are not obtained and analyzed as required, 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 RE UIREMENTS 4.4.3. 1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:

a.

b.

Primary containment atmosphere particulate and gaseous monitoring 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

CHANNEL FUNCTIONAL TEST at least once per 31 days and a

CHANNEL CALIBRATION at least once per 18 months.

Drywell floor drain sump level monitoring system-performance of a I

CHANNEL FUNCTIONAL TEST at least once per 31 days and a

CHANNEL CALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 2 3/4 4-6 Amendment No.

53

REACTOR COOLANT SYSTEH OPERATIONAL LEAKAGE

'IMITING CONDITION FOR OPERATION 3.4.3.2

'a ~

b.

C.

d.

e.

Reactor coolant system leakage shall be limited to:

No PRESSURE BOUNDARY LEAKAGE.

5 gpm UNIDENTIFIED LEAKAGE.

25 gpm total leakage averaged over any 24-hour period.

1 gpm leakage at a reactor coolant system pressure of 1000 a 10 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 4-hour period.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a0 b.

C.

d.

e.

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 COLO SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system leakage greater than tge 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 COLO 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 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 one closed manual or deactivated automatic valve, 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 one or more of the high/low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1 inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm pressure at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 4-hour period, identify the source of leakage increase as not service sensitive Type 304 or 316 austenitic stainless steel 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 .

SUSQUEHANNA - UNIT 2 3/4 4-7

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and b.

Monitoring the drywell floor drain sump level at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

Determining the total IDENTIFIED LEAKAGE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 by leak testing pursuant to Specification 4,0.5 and verifying the aakage of each valve to be within the specified limit:

a.

At least once per 18 months, and b.

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.

4.4. 3. 2. 3 The high/low pressure interface valve leakage pressure monitors shal 1

be demonstrated OPERABLE with the alarm setpoints per Table 3.4.3.2-1 by performance of a:

a.

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

CHANNEL CALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 2 3/4 4-8 Amendment No. 53

ML17156B145

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