ML17158B960
| ML17158B960 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/25/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17158B961 | List: |
| References | |
| NPF-14-A-163, NPF-22-A-134 NUDOCS 9703030441 | |
| Download: ML17158B960 (12) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENNSYLVANIA POWER IGHT COMPANY LLEGHENY LECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 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 L Light Company, dated February 2,
- 1996, as supplemented September 23,
- 1996, 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.
970303044i 970225 PDR ADOCK 05000387 P
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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) echnical S eci ications and Env'ronmental rotection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
163 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 amendm'ent is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATOR COMMISSION
Attachment:
Changes to the Technical Specifications J
n
. Stolz, Director
~
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o ect D>rectorate I-2
'sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
February 25, 1997
TTACHMENT TO LICENSE AMENDMENT NO.
FAC LITY OPERATING LICENSE NO, N F-14 OCKET NO. 50-387 Replace the following page of the Appendix A Technical Specifications with enclosed page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
REMOVE 3/4 6-2 INSERT 3/4 6-2
LIMITINGCONDITION FOR OPERATION 3,6.1.2 Primary containment leakage rates shall be limited to:
a, An overall integrated leakage rate (Type A test) in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.
b.
A combined leakage rate in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, 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'ydrostatically teak tested per Table 3.6.3-1, subject to Type B and C tests.
0c. 'Less than or equal to 100.scf per hour for any one main steam isolation valve and a combined maximum pathway leakage rate of 8 300 scf per hour for all four main steam lines through the isolation valves when tested at either Pt, 22.5 psig, or P~.
d.
Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tested in accordance with Specification 6.8,5, Primary Containment Leakage Rate Testing Program.
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 P,.
Y:
When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1
~
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With:
a.
The measured overall integrated primary containment leakage rate (Type A test) not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, 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" and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, or Pc. 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 exceedihg 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 gpmp Exemption to Appendix "J" of 10 CFR 50.
Deletion of the MSIV Leakage Control System was approved in Amendment No. 151 and implemented during the U1 9RIO.
SUSQUEHANNA - UNIT 1 3/4 6-2 Amendment No. 29-,-$ 5$ -,-458, 163
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA OWE
& LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELEC RIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE'mendment No.
134 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 February 2,
- 1996, as supplemented September 23,
- 1996, 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) Tech ical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
1 34 and the Environmental Protection'lan 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 30 days after its date of issuance.
FOR THE NUCLEAR REGU TORY COMMISSION J
F. Stolz, Director<'ect Directorate I-2
'sion of Reactor Projects I/II ffice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 25, 1997
TTACHMENT TO LICENSE AMENDMENT NO.
4 FACILITY OPERATING LICENSE NO. NPF-22 OCK T NO. 50-388 Replace the following page of the Appendix A Technical Specifications with enclosed page.
The revised page is.identified by Amendment number and contains vertical lines indicating the area of change.
REMOV 3/4 6-2 INSERT 3/4 6-2
LIMITINGCONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
a.
An overall integrated leakage rate IType A test) in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.
b.
A combined leakage rate in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves, mein steam line drain valves and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type 8 and C tests.
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 either P22.5 psig, or P,.
I d.
Less than or equal to 1.2 scf per hour for any one main steam line drain valve when tested in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program.
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 P,,
MBLlQMILIIY: When PRIMARY CONTAINMENTINTEGRITY is required per Specification 3.6.1.1.
hGIIQH:
With:
a.
The measured overall integrated primary containment leakage rate (Type A test) not in accordance with Specification 6.8.5, Primary Containment Leakage Rate Testing Program, 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 tests not in accordancewith Specification 6.8.5, Primary Containment Leakage Rate Testing Program, or
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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 draid 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 3/4 6-2 Amendment No. 42k",-029, 134