ML20101B181
| ML20101B181 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/08/1996 |
| From: | Hopkins J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20101B184 | List: |
| References | |
| NUDOCS 9603140104 | |
| Download: ML20101B181 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION y*****)
WASHINGTON, D.C. 30e06-0001 THE CLEVELAND ELECTRIC ILLLDIINATING COMPANY. ET AL.
DOCKET NO. 50-440 4
PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. NPF-58 1.
The unclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by The Cleveland Electric Illuminating Campany, Centerior Service Company, Duquesne Light Company, Ohio i
Edison Company, Fennsylvania Power Company, and Toledo Edison Company
{
i (the licensees) dated January 16, 1996, as supplemented on March 1, 1
1996, 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 (1) 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 la 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 and safety of the public; and J
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.
i 2.
Accorengly, the license is amended by changes to the Technical Specifi-cations, as indicated in the attachment to this license amendment, and 4
paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
9603140104 960308 PDR ADOCK 05000440 P
(2) Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 82 are hereby incorporated into this license.
The Cleveland Electric Illuminating Company 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 shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMISSION T'
~U
//Jon B. Hopkins, Senior Project Manager
~ Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
March 8, 1996
\\
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440' Replace the following pages of the Appendix "A" Technical Specifications including the issued but not yst implemented Improved Technical Specifications (ITS) with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-16 3/4 6-16 ITS 3.6-59 ITS 3.6-59 ITS 3.6-60 ITS 3.6-60
CONTAINMENT SYSTEMS DRYWELL BYPASS LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.2.2 Drywell bypass leakage shall be less thpn or equal to 10% of the minimum acceptable A/4 design value of 1,68 ft APPLICABILITY: When DRYWELL INTEGRITY is required per Specification 3.6.2.1.
ACTION:
With the drywell bypass leaka A/A design value of 1.68 ft.pe greater than 10% of the minimum acceptable
, restore the drywell bypass leakage to within the limit prior to increasing reactor coolant system temperature above 200*F.
SURVEILLANCE RE0VIREMENTS 4.6.2.2 The drywell bypass leakage rate test shall be conducted at least once per 18 months
- at an initial differential pressure of 2.5 psi and the A/#
shall be calculated from the measured leakage. One drywell air lock door shall remain open during the drywell leakage test such that each drywell door is leak tested during at least every other leakage rate test.
If any drywell bypass leakage test fails to meet the specified limit, the schedule for subsequent tests shall be reviewed and approved by the Commission.
If two consecutive tests fail to meet the limit, a test shall be performed at least every 9 months until two consecutive tests meet the limit, at which time the 18 month test schedule may be resumed.
l The performance of the drywell bypass leakage rate test is extended to the sixth refueling outage and need not be performed during the fifth refueling outage.
j PERRY - UNIT 1 3/4 6-16 Amendment No. 82 l
Drywell 3.6.5.1 3.6 CONTAI MENT SYSTEMS 3.6.5.1 -Drywell LC0 3.6.5.1-The drywell shall be OPERABLE.
' ' ~
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Drywell inoperable.
A.1 Restore drywell to I hour OPERABLE status.
B.
Required Action and B.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
AtiD B.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> i
PERRY - UNIT 1 3.6-59 Amendment No. W,82
Drywell 3.6.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1.1 Verify bypass leakage is less than or
NOTE-----
equal to the bypass leakage limit.
The performance However, during the first unit startup of the drywell following bypass leakage testing bypass leakage performed in accordance with this SR, the test is acceptance criterion is s 10% of the extended to the drywell bypass leakage limit.
sixth refueling outage and need not be performed during the fifth refueling i
outage.
i 18 months 4
SR 3.6.5.1.2 Visually inspect the exposed accessible Once prior to interior and exterior surfaces of the performance of i
drywell.
each Type A test required by SR 3.6.1.1.1.
i i
j PERRY - UNIT 1 3.6-60 Amendment No. l>$/,82