ML17158A846
| ML17158A846 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/15/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17158A847 | List: |
| References | |
| NPF-14-A-151, NPF-22-A-121 NUDOCS 9508230388 | |
| Download: ML17158A846 (35) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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.
151 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated November 21,
- 1994, as supplemented by letters dated February 21,
- 1995, March 28, 1995, April 10,
- 1995, May 24,
- 1995, and June 23,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 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 Commission'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 51 of the Commission's regulations and all applicable requirements have been satisfied.
9'508230388 9508i5 PDR ADQCK 05000387' PDR j
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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)
Te ic S ec
'catio s
and v
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Protect an The Technical Specifications contained in Appendix A, as revised through Amendment No.
151 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPKL 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 and is to be implemented upon the restart of the unit after its 9th refueling and inspection outage.
FOR THE NUCLEAR REGULATORY COMMISSION Jo F. Stolz, Director P
o ect Directorate I-2 D> ision of Reactor Projects I/II
. Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 15, 1995
TACHMENT TO LICENSE AMENDM NT O. 151 ACILITY OPERATING LICENSE NO. NPF-14
~ME NO.
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.
REMOVE V11 X1V 3/4 6-2 3/4 6-3 3/4 6-7 3/4 6-22 3/4 6-27 3/4 8-31 B 3/4 6-1 INSERT V11 X1V 3/4 6-2 3/4 6-3 3/4 6-22 3/4 6-27 3/4 8-31 B 3/4 6-1
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LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity Primary Containment Leakage
.... ~
Primary Containment Air Locks.............
~
Primary Containment Structural Integrity..
... 3/4 6-1
~ 3/4 6-2
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~
~ ~
~ ~ ~ ~ 3/4 6 5
~ 3/4 6-8 Drywell and Suppression Chamber Internal Pressure.
Drywell Average AirTemperature Drywell and Suppression Chamber Purge System
~. ~
3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber.......~.........
~. ~, ~..
Suppression Pool Spray Suppression Pool Cooling.
3/4.6.3 PRIMARY CONTAINMENTISOLATIONVALVES 3/4.6.4 VACUUMRELIEF 3/4.6.5 SECONDARY CONTAMINATION Secondary Containment Integrity
. 3/4 6-9
~ 3/4 6-10
........ 3/4 6-11
. 3/4 6-12
...... 3/4 6-15
.... 3/4 6-16 3/4 6-17 3/4 6-29 3/4 6-31 Secondary Containment Automatic Isolation Dampers.....~...........~........
3/4 6-32 Standby Gas Treatment System...............,.............
~. ~. ~. ~
3/4.6.5 PRIMARY CONTAINMENTATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen
.. 3/4 6-34 Recombiner Systems........~..........
~, ~..~....~........................
~ ~..
3/4 6-37 Drywell Air Flow System 3/4 6-38 Drywall and Suppression Chamber Oxygen Concentration.~... ~. ~ ~ ~.......... 3/4 6-39 SUSQUEHANNA - UNIT 1 VII Amendment No.
151
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E BASES 3/4.5.1 and 3/4.5.2 ECCS-OPERATING AND SHUTDOWN.............
~
3/4.5.3 SUPPRESSION CHAMBER
. B 3/4 5-1
... 8 3/4 5-2 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity Primary Containment Leakage Primary Containment Air Locks..
Primary Containment Structural Integrity... ~.~...... ~ ~.~... ~. ~. ~. ~.~... ~.~...
.... B 3/4 6-1 B 3/4 6-1 B 3/4 6-1 8 3/4 6-2 3/4.6.2 Drywell and Suppression Chamber Internal Pressure......
~. ~,~................
~ ~ B 3/4 6-2 Drywall Average AirTemperature... ~ ~~.......
~.~...................~.........~.......
~ B 3/4 6-2 Drywall and Suppression Chamber Purge System...........
~.~.........~...~.... B 3/4 6-2 DEPRESSURIZATION SYSTEMS.............................,...,......................
B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENTISOLATIONVALVES 3/4.6.4 VACUUM RELIEF 8 3/4 6-4 B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 6 5 3/4.6.6 PRIMARY CONTAINMENTATMOSPHERE CONTROL B 3/4 6-5 SUSQUEHANNA - UNIT 1 rdv Amendment No.
151
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LIMITINGCONDmON FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to L1.0 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P45.0 psig, b.
A combined leakage rate of less than or equal to 0.60 L, for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests when pressurized to P45.0 psig.
c.
'Less than or equal to 100 scf per hour for any one main steam isolation valve and a combined maximum pathway leakage rate of 6 300 scf per hour for all four main steam lines through the isolation valves when tested at P22.5 psig.
d.
'Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tested at P45.0 psig.
e.
A combined leakage rate of less than or equal to 3.3 gpm for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 P49.5 psig.
When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.
hQIIQH:
With:
a.
The measured overall integrated primary containment leakage rate exceeding 0.75 Lor b.
The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves', main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C testes exceeding 0.60 Lor c.
The measured leakage rate exceeding 100 scf per hour for any one main steam isolation valve or a total maximum pathway leakage rate of ) 300 scf per hour for all four main steam lines through the isolation valves, or d.
The measured leak rate exceeding 1.2 scf per hour for any one main steam line drain valve, or e.
The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 3.3
- gpm, Exemption to Appendix "J" of 10 CFR 50.
SUSQUEHANNA - UNIT 1 3/4 6-2 Amendment No. gg 151
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LIMITINGCONDITION FOR OPERATION (Continued)
~gg}g IContinued).
restore:
a.
The overall integrated leakage rate to less than or equal to 0.75 Land b.
The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type 8 and C tests to less than or equal to 0.60 Land c.
The leakage rate to less than or equal to 11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage rate to 5300 scf per hour for all four main steam lines through the isolation valves, and d.
The leakage rate to less than or equal to 1.2 scf per hour for any one main steam line drain valve, and e.
The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200'F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A Overall Integrated'Containment Leakage Rate tests shall be conducted at 40 2 10 month intervals during shutdown at P45.0 psig, during each 10-year service period.'.
If any periodic Type A test fails to meet.75 L the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet.75 I, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet.75 Lat which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1
~
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L 2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P45.0 psig.
Exemption to Appendix J of 10CFR50.
SUSQUEHANNA - UNIT 1 3/4 6-3 Amendment No. ygy 151
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TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINIVIENTISOLATION VALVES Valve Function and Number Automatic Isolation Valves (Continued)
Maximum Isolation Time (Seconds)
Isolation Signal(s)"
HV-1 5766 HV-1 5768 30 30 B,Z B,Z HV-155F075 HV-1 55F079 15 15 LB,Z LB,Z HV-149F062 HV-149F084 10 10 KB,Z KB,Z C51-J004 A,B,C,D,E A,Z SV-157100 A,B SV-157101 A,B SV-157102 A,B SV-157103 A,B SV-1 57104 SV-1 571 05 SV-1 57106 SV-1 57107 N/A N/A N/A N/A N/A N/A N/A N/A B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y HV-141F032 A,B HV-14182 A,B HV-149F01 3 1-49-020 SUSQUE~ <"INA-UNIT 1 3/4 6-22 Amendment No. Qg, fpf,151
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENTISOLATION VALVES Valve Function and Number Excess Flow Check Valves (Continued)
XV-143F003 A,B XV-143F004 A,B XV-143F009 A,B,C,D XV-143F010 A,B,C,D XV-143F011 A,B,C,D XV-143F012 A,B,C,D XV-143 F040 A,B,C, D XV-143F057 A,B, XV-142F041 XV-142F043 XV-142F045 XV-142F047 XV-142F051 XV-142F053 XV-142F055 XV-142F057 XV-142F059 XV-142F061 XV-14201 XV-14202 A,B A,B A,B A,B,C,D A,B,C,D A,B,C,D,E,F,G,H,L,M,N,P,R,S,T,U, XV-141F070 A,B,C,D XV-141F071 A,B,C,D XV-141F072 A,B,C,D XV-141F073 A,B,C,D XV-141 F009 SUSQUEHANNA-UNIT 1 3/4 6-27 Amendment No.
gg, 151
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TABLE 3.8.4.2.1-1 (Continued)
MOTOR OPERATED VALVESTHERMALOVERLOAD PROTECTION CONTINUOUS HV-E11-1F028B HV-E11-1F047B HV-E1 1-1F01 6B HV-E11-1F003B HV-E11-1F017B HV-E21-1F031 B HV-E21-1F001 B HV-E11-1F103B HV-E1 1-1 F075 B HV-E11-1F073B HV-E11-1F006D HV-E1 1-1F004D HV-E1 1-1F024B HV-E21-1F015B HV-E21-1F004B HV-E21-1F005B HV-E51-1F045 HV-E51-1 F01 2 HV-E51-1F01 3 HV-15012 HV-E51-1F046 HV-E51-1F008 HV-E51-1F031 HV-E51-1F010 Valve Number System(s)
Affected RHR RHR RHR RHR RHR CS CS RHR RHRSW RHRSW RHR RHR RHR CS CS CS
. RCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC SUSQUEHANNA - UNIT 1 3/4 8-31 Amendment No.
gg,151
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BASES PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limitthe site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 45.0 psig, P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
Operating experience with main steam line isolation valves and main steam line drain'valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.
The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix "J" of 10 CFR Part 50 with the exception of exemptions granted for main steam isolation and drain valve leak testing and testing airlocks after each opening.
The frequency for performing the Type A tests is consistent with the requirements of 10 CFR 50 Appendix "J" with the exception of the exemption granted to the schedular requirements of Section III.D.1(a).
The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the primary containment leakage rate given in Specifications 3.6.1.1 and 3.6,1.2.
The specification makes allowances for the fact
'that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation, Only one closed door in each air lock is required to maintain the integrity of the containment.
SUSQUEHANNA - UNIT 1 8 3/4 6-1 Amendment No. f/',151
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 121 License No.
NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application.for the amendment filed by the Pennsylvania Power Light Company, dated November 21,
- 1994, as supplemented by letters dated February 21,
- 1995, March 28, 1995, April 10,
- 1995, May 24,
- 1995, and June 23,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 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 w'ith the Commission'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 51 of the Commission'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-22 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.
121 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.
3.
This license amendment is effective as of its date of issuance and is to be implemented within 60 days after its date of issuance.
FOR THE NUCLEAR REGU ATORY COMMISSION J
Stolz, Director P
ect Directorate I-Dsvision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 15, 1995
TTACHMEN TO LICENSE AMENDME NO.
121 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.
REMOV vi )
xiv 3/4 6-2 3/4 6-3 3/4 6-7 3/4 6-22 3/4 6-27 3/4 8-33 B 3/4 6-1 INSERT vii Xiv 3/4 6-2 3/4 6-3 3/4 6-22 3/4 6-27 3/4 8-33 B 3/4 6-1
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LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS SKGXIQH 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity...........~..........
~~..................
~. 3/4 6-1 Primary Containment Leakage.....
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ 3/4 6 2 Primary Containment AirLocks.........~.......,......................
3/4 6-5 Primary Containment Structural Integrity............................................
3/4 6-8 Drywell and Suppression Chamber Internal Pressure.............,.............
3/4 6-9 Drywell Average AirTemperature..............,
~. ~. ~. ~ ~ ~. ~. ~. ~
~
....... 3/4 6-10 Drywell and Suppression Chamber Purge System..........~...........
3/4 6-11 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber Suppression Pool Spray........~................~.....~...,..
Suppression Pool Cooling..
. 3/4 6-12
. 3/4 6-15
.. 3/4 6-16 3/4.6.3 PRIMARY CONTAINMENTISOLATIONVALVES..................................
3/4 6-17 3/4.6.4 VACUUMRELIEF.......
~..~..........
. 3/4 6-29 3/4.6.5 SECONDARY CONTAMINATION Secondary Containment Integrity...........~......,.......,...,..~.......
~. ~. ~.~..... 3/4 6-31 Secondary Containment Automatic Isolation Dampers..........................
3/4 6-34 Standby Gas Treatment System..................
~.~... ~. ~.~... ~
3/4.6.6 PRIMARY CONTAINMENTATMOSPHERE CONTROL Drywall and Suppression Chamber Hydrogen Recombiner Systems.
Drywell Air Flow System.
. 3/4 6-36 3/4 6-39
. 3/4 6-40 Drywell and Suppression Chamber Oxygen Concentration.................... 3/4 6-41 SUSQUEHANNA - UNIT 2 vll Amendment No.
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BASES 3/4.5.1 and 3/4.5.2 ECCS-OPERATING AND SHUTDOWN.
3/4.5.3 SUPPRESSION CHAMBER.
. B 3/4 5-1 8 3/4 5-2 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity...................
~. ~.~.........~.....
B 3/4 6-1 Primary Containment Leakage...~................,.......,.....,........................
B 3/4 6-1 Primary Containment Air Locks......................,......,........
~,......
Primary Containment Structural Integrity......'.......~....................
~..
Drywall and Suppression Chamber Internal Pressure.....
B 3/4 6-1 B 3/4 6-2
.. B 3/4 6-2 Drywall Average AirTemperature
...,...... B 3/4 6-2 Drywall and Suppression Chamber Purge System...........,,
. B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENTISOLATIONVALVES..............................,...
B 3/4 6-4 3/4.6.4 3/4.6.5 VACUUMRELIEF..........................................................................
B 3/4 64 SECONDARY CONTAINMENT...,........................................~............
B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENTATMOSPHERE CONTROL. ~. ~.~...........
~. ~.~... ~. B 3/4 6-5 SUSQUEHRNNA - UNIT'2 tdv Amendment No. 1p)
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LIIVIITINGCONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to L1.0 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P45.0 psig.
b.
A combined leakage rate of less than or equal to 0.60 L, for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests when pressurized to P45.0 psig.
c.
'Less than or equal to 100 scf per hour for any one main steam isolation valve and a combined maximum pathway leakage rate of 5 300 scf per hour for all four main steam lines through the isolation valves when tested at P22.5 psig.
d.
"Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tested at P45.0 psig.
e.
A combined leakage rate of less than or equal to 3.3 gpm for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 P49,5 psig.
When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.
ELQIlQH:
With:
a.
The measured overall integrated primary containment leakage rate exceeding 0.75 i.or b.
The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves', main steam line drain valves'nd valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type 8 and C testes exceeding 0.60 Lor c.
The measured leakage rate exceeding 100 scf per hour for any one main steam isolation valve or a total maximum pathway leakage rate of > 300 scf per hour for all four main steam lines through the isolation valves, or d.
The measured leak rate exceeding 1.2 scf per hour for any one main steam line drain valve, or e.
The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 3.3
.gpm, Exemption to Appendix "J" of 10 CFR 50.
SUSQUEHANNA - UNIT 2 314 6-2 Amendment No. 121
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uMITINGCONDITION FOR OPERATION (Continued)
~
hQIN5 (Continued) restore:
a.
The overall integrated leakage rate to less than or equal to 0.75 Land b.
The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, main steam line drain valves and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type 8 and C tests to less than or equal to 0.60 Land c.
The leakage rate to less than or equal to 11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage rate to 5300 scf per hour for all four main steam lines through the isolation valves, and d.
The leakage rate to less then or equal to 1.2 scf per hour for any one main steam line drain valve, and e.
The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 3.3 gpm, prior to increasing reactor coolant system temperature above 200'F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45A - 1972:
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 k 10 month intervals during shutdown at P45.0 psig, during each 10-year service period.
b.
If any periodic Type A test fails to meet.75 L the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet.75 La Type A test shall be performed at least every 18 months until two consecutive Type A tests meet.75 I, at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L 2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the, containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P45.0 psig.
¹ Exemption to Appendix J of 10CFR50.
SUSQUEHANNA - UNIT 2 3/4 6-3 Amendment No 89) 121
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENTISOLATION VALVES Valve Function and Number Automatic Isolation Valves (Continued)
Maximum Isolation Isolation Signal(s)
'ime (Seconds)
HV-25766 HV-25768 35 30 B,Z B,Z HV-255F075 HV-255F079 15 15 LB,Z LB,Z HV-249F062 HV-249F084 10 10 KB,Z KB,Z C51-J004 A,B,C,D,E A,Z b.
SV-257100 A,B SV-257101 A,B SV-257102 A,B SV-257103 A,B SV-257104 SV-257105 SV-257106 SV-257107 N/A N/A N/A N/A N/A N/A N/A N/A B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y HV-241F032 A,B HV-24182 A,B HV-249F01 3 2-49-020 SUSQUEHANNA - UNIT2 3/4 6-22 Amendmen(No.
S)i "~~ "~1
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENTISOLATIONVALVES Valve Function and Number Excess Flow Check Valves (Continued)
XV-243F003 A,B XV-243F004 A,B XV-243F009 A,B,C, D XV-243F010 A,B,C,D XV-243F011 A,B,C,D XV-243F012 A,B,C,D XV-243F040 A,B,C,D XV-243F057 A,B, XV-242F041 XV-242F043 XV-242F045 XV-242F047 XV-242F051 XV-242F053 XV-242F055 XV-242F057 XV-242F059 XV-242F061 XV-24201 XV-24202 A,B A,B A,B A,B,C,D A,B,C,D A,B,C,D,E,F,G,H,L,M,N,P,R,S,T,U, XV-241F070 A,B,C,D XV-241F071 A,B,C,D XV-241F072 A,B,C,D XV-241F073 A,B,C,D XV-241 F009 SUSQUEHANNA - UNIT2 3I4 6-27 Amendment No.
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TABLE3.8A.2.1-1 (Cantinued)
MOTOR OPERATED VALVESTHERMALOVERLOAD PROTECTION CONTINUOUS C
HV-E1 1-2F021 8 HV-E11-2F0108 HV-E11-2F0048 HV-E11-2F0078 HV-E11-2F1048 HV-E11-2F0268 HV-E1 1-2F0288 HV-E1 1-2F0478 HV-E1 1-2F01 68 HV-E11-2F0038 HV-E1 1-2F01 78 HV-E21-2F031 8 HV-E21-2F0018 HV-E11-2F1038 HV-E11-2F0758 HV-E11-2F0738 HV-E11-2F006D HV-E1 1-2F004D HV-E11-2F0248 HV-E21-2F0158 HV-E21-2F0048 HV-E21-2FOOSB HV-E51-2F045 HV-E51-2F012 HV-E51-2F013 HV-25012 Valve Number System(s)
Affected RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR CS CS RHR RHRSW RHRSW RHR RHR RHR CS CS Cs RCIC RCIC RCIC RCIC SUSQUEHANNA-UNIT2 3/4 8-33 Amendment No. gg,1p1
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BASES PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, willlimitthe site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 45.0 psig, P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0,75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
Operating experience with main steam line isolation valves and main steam line drain valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.
The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix "J" of 10 CFR Part 50 with the exception of exemptions granted for main steam isolation and drain valve leak testing and testing airlocks after each opening.
The frequency for performing the Type A tests is consistent with the requirements of 10 CFR 50 Appendix "J" with the exception of the exemption granted to the schedular requirements of Section III.D.1(a).
The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the primary containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2.
The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation.
Only one closed door in each air lock is required to maintain the integrity of the containment.
SUSQUEHANNA - UNIT 2 B 3/4 6-1 Amendment No.
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