ML20036B806
| ML20036B806 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/20/1993 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036B807 | List: |
| References | |
| NUDOCS 9306030103 | |
| Download: ML20036B806 (8) | |
Text
.
'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION n
g
- y WASHINGTON, D. C. 20555 k......o#
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.174 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated March 11, 1993, as supplemented by letter dated May 13, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
9306030103 930520' PDR ADDCK 05000277 P
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ib Charles L.
11er, 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: May 20, 1993
ATTACHMENT TO LICENSE AMENDMENT NO. 174 FACILITY OPERATING LICENSE NO. OPR-44 DOCKET NO. 50-277 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
Remove Insert 7
7
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Unit 2 f
PBAPS 1.0 DEFINITIONS (Cont'd)
- outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
Reportable Event - A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
Run Mode - In this mode the reactor system pressure is at or above 850 psig and the reactor protection system is energized wit.P APRM protection (excluding the 154 high flux trip) and RBM interlocks in service.
Safety Limit - The safety limits are limits below which the reasonable maintenance of the cladding and primary systems are assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit operation.
Operation beyond such a limit may not in itself result in serious consequences, but it indicates an operational deficiency subject to regulatory review.
Secondary Containment Integrity Secondary Containment integrity means that the reactor building is intact and the following conditions are met:
1.
At least one door in each access opening is closed.
2.
The standby gas treatment is operable.
3.
All Reactor Buildinq ventilation system automatic isolation valves are operable or deactivated in the isolation position.
Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
Placing the mode switch to the shutdown Shutdown Mode position initiates a reactor scram.
After about 2 seconds, this SCRAM signal is bypassed.
The SCRAM logic cannot be reset until a 10 second timer is complete. The SCRAM can then be reset to restore the normal valve line-up in the control rod drive hydraulic system. Amendment No. 102, 110, I!7, 174 v
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UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION c,
g E
WASHINGTON, D. C. 20S55
\\...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3' AMENDMENT TO FACILITY'0PERATING LICENSE Amendment No. 177 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated March 11, 1993, as supplemented by letter dated May 13, 1993, complies with the standards and-requirements of the Atomic Energy Act of 1954, as amended (the Act),' and the Commission's rules and 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 rules and 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or 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' Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
4
'. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.177, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
~%
Charles L. Miller, Director fDivisionofReactorProjects-I/II Project Directorate I-2 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 20, 1993
9:
ATTACHMENT TO LICENSE AMENDMENT N0.177 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET N0. 50-278 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Remove Insert l
7 7
i i
I i
i
r i=q
\\
Unit.3 f
PBAPS 1.0 DEFINITIONS-(Cont'd)
- outage, the required surveillance' testing need not be performed until the next regularly scheduled outage.
Reportable Event - A reportable event shall be any of those'-
conditions specified in Section 50.73 to 10 CFR Part 50.
Run-Mode - In this mode the reactor system pressure is'at or above 850 psig and the reactor protection system is energized" with APRM protection (excluding the 154 high flux trip)~and.
t RBM-interlocks in service.
Safety Limit - The safety. limits are limits be'ow which the l
reasonable maintenance of the cladding and primary systems are-assured.
Exceeding such a limit requires unit shutdown.and.
i review by the Nuclear Regulatory Commission before resumption
)
of unit operation.
Operation beyond'such a limit may not in-1 itself result in serious consequences, but it indicates an j
operational deficiency subject to regulatory review.-
Secondary containment Integrity.
Secondary. Containment-integrity means that the reactor building is. intact and the following conditions are met:
j 1.
At least one door in each access opening is closed.
1 2.
The standby gas treatment is~ operable.
[
3.
All -RJactor Building : ventilation system automatic isolation - valves are operable or-deactivated in the-isolation position.
Shutdown - The reactor is in a' shutdown condition when. the reactor mode switch is in the shutdown mode. position andno core alterations are being performed.
Shutdown Mode Placing - the mode switch to the : shutdown position initiates a reactor scram.
After about 2 seconds, this SCRAM signal is bypassed..
The SCRAM logic cannot' be -
reset until a-10 second timer is complete.. The SCRAM can then j
be reset to restore.the normal valve line-up'in the control
)
rod drive hydraulic system.
q
. ; Amendment No. IN, !!3,- 12y,177
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