ML17157B875
| ML17157B875 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/24/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157B874 | List: |
| References | |
| NUDOCS 9207020253 | |
| Download: ML17157B875 (17) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 PENNSYLVANIA POWER 5, LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
121 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 August 16, 1991 and supplemented by letter dated May 29,
- 1992, 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 assur ance:
(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.
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:
9207020253 920624 PDR ADOCK 05000387 P
(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 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:.
June 24.
1992 Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
121 FACILITY OPERATING 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 6-3 3/4 6-4 B 3/4 6-1 B 3/4 6-2 INSERT 3/4 6-3 3/4 6-4*
B 3/4 6-1 B 3/4 6-2*
C
NT INM Y TEM BA E 4..
IM NTAINME T 4..1 PRIIVlA NTAINMENTINTEGRITY 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.
4..1.2 PRIMARY ONTAINMENTLEAKA E The limitations on primary containment leakage rates ensure that the total containment leakage volume willnot 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 the airlocks after each opening, The frequency for performing the Type A tests is consistent with the requirements of 10CFR50 Appendix "J with the exception of the exemption granted to the schedular requirements of Section III.D.1(a).
4.
1.
PRIMARY NTAINMEN AIR LO K
The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARYCONTAINMENTINTEGRITYand 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.
4..1.4 M
LEA E
NTR L
Y TEM Calculated doses resulting from the maximum leakage allowance forthe main steamline isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided the main steam line system from the isolation valves up to and including the turbine condenser remains intact.
Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.
The requirement for the leakage control system willreduce the untreated leakage from the MSIVs when isolation of the primary system and containment is required.
SUSQUEHANNA - UNIT 1 B 3/4 6-1 Amendment No. Jgl
CONTAINMENT SYSTEMS-BASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY
~
This limitation ensures that the structural integrity of the containment.
will be maintained comparable to the original design standards for the life of the unit.
Structural integrity is required to ensu~e that the containment will withstand the maximum pressure of 45.0 psig in the event of a LOCA.
A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6. 1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression in chamber internal pressure ensure that the containment peak pressure of 45.0 psig does not exceed the design pressure of 53 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5 psid.,
The limit of 2.0 psig for initial positive containment pressure will limit the total pressure to 45. 0 psig which is less than the design pressure and is consistent with the safety analysis.
3/4.6. 1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340 F
during LOCA conditions and is consistent with the safety analysis.
3/4.6.1.8 ORYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control.
Until these valves have been demonstrated capable of closing during a LOCA or steam line break accident, they shall be blocked so as not to open more than 50~.
Until these valves have been demonstrated capable of closing within the times assumed in the safety analysis, they shall not be open more than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in any consecutive 365 days.
Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.
The 0.60 L
leakage limit shall not be exceeded when the leakage rates determined Sy the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
SUSQUEHANNA - UNIT 1 B 3/4 6-2 Amendment No.
29
NTAINMENT Y TEM LIMITIN NDITION FOR OPERATION Con inued
~AT~I (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 B and C tests to less than or equal to 0.60 Land
- c. 'he leakage rate to less than or equal to 46 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.
URVEILLANCEREQUIREMENTS 4.6.1.2 a0 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:
Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 a 10 month intervals during shutdown at P45.0 psig, during each 10-year service period.>>
b.
Ifany 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.
Iftwo 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 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:
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.
3.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
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, 121
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.
Type B and C tests shall be conducted with gas at P
, 45:0 psig,* at intervals no greater than 24 months except for testI involving:
1.
Air locks, 2.
Main steam line isolation valves and main steam line drain
- valves, 3.
Containment isolation valves in hydrostatically tested lines which penetrat'e the primary containment, and 4.
Purge supply and exhaust isolation valves with resilient material seals.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves and main steam line drain valves shall be leak tested at least once per 18 months.
g.
Containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at least once per 18 months.
h.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.8.2.
The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.l.2.c, 4.6.1.2.d, and 4.6.1.2.e.
I Unless a hydraulic test is required per Table 3.6.3-1.
SUSQUEHANNA - UNIT 1 3/4 6-4 Amendment No.
36
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 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.
89 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 5
Light Company, dated August 16, 1991 and supplemented by letter dated May 29,
- 1992, 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 sati sfi ed.
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 1
The Technical Specifications contained in Appendix A, as revised through Amendment No.
89 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 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~g, '4..J. (g~(4 Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
~une 24
"4e
ATTACHMENT TO LICENSE AMENDMENT NO.
89 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.*
REMOVE 3/4 6-3 3/4 6-4 B 3/4 6-1 B 3/4 6-2 INSERT 3/4 6-3 3/4 6-4*
B 3/4 6-1 B 3/4 6-2*
4.
NTA NMENT Y TEM BASES 4..'I P IM RY NTAINMEN 4..1.
PRIMARY NTAINMENTINTE RITY 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.
4.6.1.2 IMARYC NTAINMENTLEAKAGE The limitations on primary containment leakage rates ensure that the total containment leakage volume willnot 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 the airlocks after each opening.
The frequency for performing the Type A tests is consistent with the requirements of 10CFR50 Appendix "J" with the exception of the exemption granted to the schedular requirements of Section III.D.1{a).
4.6.1.
P IMARY NTAINIVIEN AIR LO K
The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARYCONTAINMENTINTEGRITYand 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.
/4..1.4 I
LEAKA E N
R TEM Calculated doses resulting from the maximum leakage allowance forthe main steamline isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided, the main steam line system from the isolation valves up to and including the turbine condenser remains intact.
Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.
The requirement for the leakage control system willreduce the untreated leakage from the MSIVs when isolation of the primary system and containment is required.
SUSQUEHANNA - UNIT 2 B 3/4 6-1 Amendment No. 89
CONTAINMENT SYSTEMS BASES 3/4. 6. 1. 5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit.
Structural integrity is required to ensure that the containment will withstand the maximum pressure of 45.0 psig in the event of a LOCA.
A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6. 1.6 DRYMELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression in chamber internal pressure ensure that the containment peak pressure of 45.0 psig does not exceed the design pressure of 53 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5 psid.
The limit of 2.0 psig for initial positive containment pressure will limit the total pressure to 45.0 psig which is less than the design pressure and is consistent with the safety analysis.
3/4.6. 1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340 F
during LOCA conditions and is consistent with the safety analysis.
3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell-and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting and pressure control.
The 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 day limit on purge valve operation is imposed to protect the integrity of the SGTS filters.
Analysis indicates that should a
LOCA occur while this pathway is bein'g utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS.
This limit is not imposed,
- however, on the subject valves when pressure control is being performed through the 2-inch bypass line, since a pressure surge through this line does not threaten the OPERABILITY of SGTS.
Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.
The 0.60 L
leakage limit shall not be a
exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
SUSQUEHANNA - UNIT 2 B 3/4 6-2
NT MEN Y TEM LIMITIN NDITI NFOROPERATI N Con inued
~AT~I (Continued) restore:
a.
The overall integrated leakage rate to less than or equal to 0.75 Land b,
C.
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 B and C tests to less than or equal to 0.60 Land The leakage rate to less than or equal to 46 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.
SURVEILLANCEREQ IREMENT 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:
aO Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 a 10 month intervals during shutdown at P,; 45.0 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.
Iftwo 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 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:
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 2 3/4 6-3 Amendment No. 89
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.
Type B and C tests shall be conducted with gas at P
, 45.0 psig,". at intervals no greater than 24 months except for test involving:
l.
Air locks, 2.
Main steam line isolation valves and main steam line drain
- valves, 3.
Containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and 4.
Purge supply and exhaust isolation valves with resilient material seals.
e.
g.
h.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
Main steam line isolation valves and main steam line drain valves shall be leak tested, at least once per 18 months.
Containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at least once per 18 months.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement
- 4. 6. 1.8.2.
The provisions of Specification 4.0.2 are not applicable to Specifica-tions 4.6. 1.2.a, 4.6.1.2.b, 4.6. 1.2.c, 4.6. 1.2d and 4.6.1.2e.
"Unless a hydraulic test is required per Table 3.6.3-1.
SUSQUEHANNA - UNIT 2 3/4 6-4