ML19340A950
| ML19340A950 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/09/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340A949 | List: |
| References | |
| NUDOCS 8009100792 | |
| Download: ML19340A950 (4) | |
Text
,
j, "' "'Guyr,t
~
'co UNITED STATES 4' 'i NUCLEAR REGULATORY COMMISSION 5.0 WASHINGTON, D. C. 20555 e.
' N. /
i c.
COMMONWEALTH EDISON COMPANY DOCKET No. 50-10 DRESDEN NUCLEAR POWER STATION UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 17 License No. DPR-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 11, 1976, 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 fo rth in 10 CFR Chapter I; i
B.
The facility will operate in confo'rmity with the application, the provisions of the Act, and t,he 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 co= mon defense and security or 'to the health and safety of the public ; and E.
The issuancesof this amendment is in accordance with 10 CFR Part 51 of the Co= mission's regulations and all applicable requirements-have been satisfied.
J l
t l
.8 0 0.910 0 7f 2
- i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
3.
This license amendment is ef fective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Sign,i by:
Dennis L. Zic-r n Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
- ,
- :[.; 0 : 1975 O
W e
e
ATTACHMENT TO LICENSE AMENDMENT NO. 17 FACILITY OPERATING LICENSE NO. DPR-2 DOCKET No. 50-10 Replace page 86 of the Technical Specifications with the attached revised page 66.
The changed area of the revised pa:.. is shown by a carginal line.
E e
e a
3.7 LIMITING CONDITI N FOR OPERATION 4.7.SURVEILI CE REQUIRFJ1ENT
~
3.7-CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability:
Applicability:
Applies to the operating status of the primary Applies to the primary containment integrity.
containment system.
Objective:
Objective:
f To verify the integrity of the primary containment.
To assure the integrity of the primary containment system.
Specification:
Spc'ification:
A.
A.
Reactor Enclosure (primary containment) integrity shall be demonstrated by 4
1.
Primary containment integrity shall be conducting Integrated Primary Containment maintained at all times except when all Leak Tests (IPCLT).
of the following occur simultaneously:
a.
IPCLT shall bc performed at a f
a.
All control rods are inserted.*
pressure of approximately 20 psig.
b.
No primary system work with the b.
If local Icak rate measurements are potential of draining the reactor.
mado prior to IPCLT, and repairs are vessel is in progress.
found to be necessary and retests con-ducted, the Icak rate difference, c.
No work is in progress over the prior to and after repair when corrected reactor vessel without the vessel to a pressure of 20 psig shall be added head in place.*
to the final integrated Icak rate result.
1 d.
No fuel transfers are in progress within primary containment.*
c.
Closure of the containment isolation valves for the purposes of the test e.
The reactor water temperature is shall t>c accomplished by the means less than 212 F.
provided for normal operation of the valves.
- - This provision not applicable with no fucI in the reactor _ vessel or containment.
4 86 Amendment No. 17
.