ML17146A482
| ML17146A482 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 08/01/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A483 | List: |
| References | |
| NUDOCS 8608110223 | |
| Download: ML17146A482 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 8 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
59 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company (the licensee),
dated May 14, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's requlations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the apolication, the provisions of the Act, and the regulations of the Commission; C.
D.
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; 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:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 59 and the Environmental Protection Plan con-tained in Appendix 8, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
seoEIXXO22i EI6OaOS PDR ADOCH, 05000387 P
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3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
Augst l lgB6 Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
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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 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
27 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for the amendment filed by the Pennsylvania Power 8
Light Company (the licensee),
dated May 14, 1986, 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.
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. 27 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PPKL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
Y 3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
August 1, 1986 Elinor G. Adensam, Director BWR Project Directorate No.
3 Division of BWR Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
59 FACILITY OPERATING LICENSE NO.
NPF<<14 DOCKET NO.
50<<387 Renlace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by Amendment numbe~
and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document comp1eteness.
RENAVE 3/4 6-31 3/4 6-31a INSERT 3/4 6-31 3/4 6-31a (overleaf)
1~
CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT"" INTEGRITY shall be maintained.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and ".
ACTION:
Nithout SECONDARY CONTAINMENT"" INTEGRITY:
a.
In OPERATIONAL CONDITION 1, 2, or 3, restore SECONDARY CONTAINMENT""
INTEGRITY 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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
In Operational Condition ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.6.5.1 a.
b.
SECONDARY CONTAINMENT"" INTEGRITY shall be demonstrated by; Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the pressure within the secondary containment is less than or equal to 0.25 inch of vacuum water gauge.
Verifying at least once per 31 days that:
la.
When the railroad bay door (No. 101) is closed; all Zone I and III hatches, removable walls, dampers, and doors connected to the railroad access bay are closed,& or i)
~Onl Zone I removable walls and/or doors are open to the rai road access shaft,¹¹ or ii)
~Onl Zone III hatches and/or dampers are open to the ras road access shaft.¹¹ lb.
When the railroad bay door (No. 101) is open; all Zone I and III hatches, removable walls, dampers, and doors connected to the railroad access bay are closed.
"When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
""Secondary Containment consists of Zone I, Zone II and Zone III or Zone I and Zone. III when Zone II is isolated from Zone I and Zone III.
During operational condition" when no operations with a potential for draining the reactor vessel are being performed, secondary containment may consist of Zone III as long as Zone I is isolated from Zone III.
¹¹Personnel ingress and egress through doors within the secondary containment is not prohibited by this specification.
SUS(UEHANNA " UNIT 1 3/4 6-31 Amendment No. 59
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued 2a.
At least one door in each access to the secondary containment zones is closed.
2b.
At least one door in each access between secondary containment zones is closed."
3.
a.
5.
All secondary containment penetrations"" not capable of being closed by OPERABLE secondary containment automatic isolation dampers and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers secured in position.
The truck bay hatch is closed.
The truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and III.
At least once per 18 months:
1.
For three zone operation with Zone II OPERABLE:
a.
Verifying that one standby gas treatment subsystem will draw down the secondary containment (Zone I and Zone III) to greater than or equal to 0.25 inches of vacuum water gavge in less than or equal to 15 seconds, and b.
Operating one standby gas treatment subsystem for one hour and maintaining greater. than or equal to 0.25 inches of vacuum water gauge in the secondary containment at a flow rate of less than or equal to 2885 cfm from Zone I and Zone III, and C.
Verifying by calculation that one standby gas treatment subsystem will maintain greater than or equal to 0.25 inches of vacuum water gauge'n the secondary containment at a flow rate of less than or equal to: 4000 cfm from Zone I, Zone II, and Zone III, or 2.
For three zone operation:
a0 Verifying that one standby gas treatment subsystem will draw down the secondary containment (Zone I, Zone II and Zone III) to greater than or equal to 0.25 inches of vacuum water gauge in less than or equal to 92 seconds, and l
"Personnel ingress and egress..through doors within the secondary containment is not prohibited by this:. specification.
"Penetration between..-secondary.
containment zones, penetrations to no-zones, and penetrations to;,the:outside'tmosphere.
SUSQUEHANNA - UNIT 1 3/4 6-31a
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Ah1END~)ENT NO.
21
ATTACHMENT TO LICENSE AMENDMENT NO.
27 FACILITY OPERATING LICENSE NO. NPF-22
'I 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 corresponding overleaf pages are also provided to maintain document completeness.
REMOVE 3/4 6-31 3/4 6-32 INSERT 3/4 6-31 3/4 6-32 (overleaf)
CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT"" INTEGRITY shall be maintained.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and *.
ACTION:
Without SECONDARY CONTAINMENT"" INTEGRITY:
a.
In OPERATIONAL CONDITION 1, 2, or 3, restore SECONDARY CONTAINMENT""
INTEGRITY 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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
In Operational Condition ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEII LANCE RE UIREMENTS 4.6.5.1 a ~
b.
SECONDARY CONTAINMENT"" INTEGRITY shall be demonstrated by; Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the pressure within the secondary containment is less than or equal to 0.25 inch of vacuum water gauge.
Verifying at least once per 31 days that:
la.
When the railroad bay door (No. 101) is closed; all Zone I and III hatches, removable walls, dampers, and doors connected to the railroad access bay are closed,¹¹ or i)
~Onl Zone I removable walls and/or doors are open to the
~alTroad access shaft,8¹ or ii)
~Onl Zone III hatches and/or dampers are open to the
~aiTroad access shaft;¹¹ lb.
When the railroad bay door (No. 101) is open; all Zone I and III
- hatches, removable walls, dampers, and doors connected to the railroad access bay are closed.
"When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
""Secondary Containment consists of Zone I, Zone II and Zone III or Zone I and Zone III'hen Zone I is isolated from Zone II and Zone III.
During operational condition" when no operations with a potential for draining the reactor vessel are being performed, secondary containment may consist of Zone III as long as Zone II is isolated from Zone III.
¹¹Personnel ingress and egress through doors within the secondary containment is not prohibited by this specification.
SUS(UEHANNA " UNIT 2 3/4 6"31 Amendment No. 27
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued) 2a.
At least one door in each access to the secondary containment zones is closed.
2b.
At least one door in each access between secondary containment zones is closed. "
3.
5.
All secondary containment penetrations"" not capable of being closed by OPERABLE secondary containment automatic isolation dampers and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers secured in position.
The truck bay hatch ts closed.
The truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and III.
C.
At least once per 18 months:
1.
For three zone operation with Zone I OPERABLE:
a ~
b.
C.
Verifying that one standby gas treatment subsystem will draw down the secondary containment (Zone II and Zohe III) to greater than or equal to 0.25 inches of vacuum water gauge in less than or equal to 15 seconds, and Operating one standby gas treatment subsystem for one hour and maintaining greater than or equal to 0.25 inches of vacuum water gauge in the secondary containment at a flow rate of less than or equal to 2960 cfm from Zone II and Zone III, and Verifying by calculation that one standby gas treatment subsystem will maintain greater than or equal to 0.25 inches of vacuum water gauge in the secondary containment at a flow rate of less than or equal to 4000 cfm from Zone I, Zone II, and Zone III, or 2.
For three zone operation:
Verifying that one standby gas treatment subsystem will draw down the secondary containment (Zone I, Zone II end
- Zone III) to greater than or equal to 0.25 inches of vacuum water gauge in less than or equal to 92 seconds, and "Personnel ingress and egress through doors within the secondary containment is not prohibited by this specification.
""Penetration between secondary containment zones, penetrations to no-zones, and penetrations to the outside atmosphere.
SUS(UEHANNA " UNIT 2 3/4 6-32