ML20087G002
| ML20087G002 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/13/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, PECO Energy Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20087G004 | List: |
| References | |
| DPR-44-A-206 NUDOCS 9508160174 | |
| Download: ML20087G002 (4) | |
Text
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1 W e:
UNITED STATES l
NUCLEAR REGULATORY COMMISSION E
f WASHINGTON, D.C. 20555-0001
/
PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.206 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated March 30, 1995, as supplemented by letter dated May 26, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission'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:
9508160174 950613 ADOCK0500g7 DR
I (2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as 1
revised through Amendment No.206, 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.
I FOR THE NUCLEAR REGULATORY COMMISSION l
M J
John F. Stolz, Director Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 13, 1995 i
-f,
.e ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. OPR-44 DOCKET NO. 50-277 i
Replace the following pages of the Appendix A Technical Specifications with i
the enclosed pages. The revised areas are indicated by marginal lines.
I REMOVE -
INSERT 177 177 i
9 i
l l
i E
p I
i i
I
Unit 2 E
.PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS L7.D Prinary Containment 4.7.D Primary Containment Iso' ation Valves Isolation Valves.
1.
During reactor power operating 1.
The primary containment conditions, all isolation isolation valve surveillance
-valves listed in Table 3.7.1
.shall be performed as follows:
and.all reactor instrument line excess flow check valves a.
At least once per.
shall be operable except as operating cycle the operable specified-in 3.7.D.2 and isolation valves that are 3.7.D.3 below, power operated and automatically initiated shall.be tested.
i
'2.
In the event any isolation for simulated automatic valve specified in Table 3.7.1 initiation and closure i
becomes inoperable for isolation, times.
maintain at least one isolation valve operable in the affected.
b.
At least once per quarter:
' penetration that is open and within j
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either: -
(1)
All normally open power operated isolation a.
Restore the inoperable valve valves (except for to operable status, or the main steam line power operated.
b.
Isolate the affected penetra-isolation valves).
j tion by use of at least shall be fully closed.
one deactivated automatic _
and reopened.**
l valve secured in the isolation 2
position *, or (2)
With the reactor power less than 75% trip main-i c.
Isolate the affected penetra-steam isolation valves tion by use of at least-individually and verify one closed manual valve
- closure time.
i or blind flange.
'j c.
At least once per week the d.
Otherwise be in at least Hot main steam line power-operated Shutdown within the next isolation valves shall be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown ~
exercised by partial closure within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and subsequent reopening.
1 2.a.
Whenever an isolation valve 1
listed in Table'3.7.1 is inoperable,.the position of at i
least one other valve in~each line having an inoperable valve shall be recorded daily.
j b.
The isolation valves specified I
in Table 3.7.1 shall be
- Isolation valves closed to demonstrated to be operable satisfy these requirements may prior to returning to service i
be reopened on an intermittent after maintenance on or replace--
)
basis under administrative control, ment of the valve, actuator, i
control or power circuit by 1
performance of a cycling test, 1
and verification of isolation time
- HPCI MO-2-23-015 is exempted from quarterly testing requirements until 2R0ll.
1
-177-Amendment No. f#, 206
.