ML20106H672
| ML20106H672 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/18/1996 |
| From: | Hopkins J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20106H674 | List: |
| References | |
| NUDOCS 9603210339 | |
| Download: ML20106H672 (6) | |
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i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 30006-0001 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
I DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. NPF-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company (CEICO), Centerior Service Company, Duquesne Light Company, Ohio Edison Company, OES Nuclear, Inc., Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated February 17, 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; 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 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 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Onerating License No. NPF-58 is hereby amended to read as follows:
9603210339 960318 PDR ADOCK 05000440 P
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r (2) Technical Snacifications The Technical Specifications contained in Appendix A and the Environmental Prctaction Plan contained in Appendix B, as revised s
through Amendment No. 83 are hereby incorporated into this license.
The Cleveland Electric Illuminating Company shall operate the facility j
in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 30 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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/ on B. Hopkins, Se'nior Project Manager J
l Project Directorate III-3 Division of Reactor Projects III/IV l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
March 10, 1996 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 83 FACILITY 6?ERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace'the following pages of the Appendix "A" Technical Specifications including the issued but not yet iglemented 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 6-3 3/4 6-3 3/4 6-4 3/4 6-4 I
1
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
An overall integ#. of less than or equal to 0.75 L,. where L is 0.20 rated leakage rate, except for the main steam line a.
isolation valves percent by weight of the primary containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,.
b.
A combined leakage rate of less than or equal to 0.60 L, isolation for all penetrations and all valves, except for main steam line valves # and valves which are hydrostatically leak tested. subject to Type B and C tests when pressurized to P,.
c.
Less than or equal to 25 scf per hour
- for any one main steam line l
through the isolation valves when tested at P,.
d.
A combined leakage rate of less than or equal to 0.0504 L, for all penetrations that are secondary containment bypass leakage paths when pressurized to the required test pressure.
e.
A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment. when tested at greater than or equal to 1.10 P,.
APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. AND 3. with the reactor coolant system ter ature greater than 200 F.
ACTION:
With: a.
The measured overall integrated primary containment leakage rate, except for the main steam line isolation valves #, exceeding 0.75 L,.
or b.
The measured combined leakage rate for all penetrations and all valves except for main steam line isolation valves # and valves which are hydrostatically leak tested, subject to Type B and C tests exceeding 0.60 L, or j
i c.
The measured leakage rate exceeding 25 scf per hour
- for any one main steam line through the isolation valves, or Exemption to Appendix J of 10 CFR 50.
One main steam line may be less than or equal to 35 scf per hour as long as total leakage rate through all four main steam lines is less than or equal to 100 scf per hour. This will remain in effect from the effective date of this amendment until the completion of Operating Cycle 6.
PERRY - UNIT 1 3/4 6-3 Amendment No. 83 i
CONTAINMENT SYSTEMS
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PRIMARY CONTAINMENT-LEAKAGE LIMITING CONDITION FOR OPERATION (Continued) 6 i
d.
The combined leakage rate for all penetrations that are secondar/
containment bypass leakage paths exceeding 0.0504 L., or e.
The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the pr'<.ery containment exceeding 1 gpm times the total number of such c ives-Restore the leakage rate to less than or equal to the above limit (s) within l' hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD l
SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 SURVEILLANCE REQUIREMENTS 4
4.6.1.2 The primary containment leakage rates shall be demonstrated at the i
following test schedule and shall be determined in conformance with the criteria i
specified in Appendix J of 10 CFR Part 50. except that the provisions of Bechtel l
l Topical Report BN-TOP-1 may be used for Type A tests having a duration less than l
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
l.
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall l
be conducted at 40 + 10 month intervals during shutdown at P, during l
each 10-year service period.
l b.
If any periodic Type A test fails to meet 0.75 L. the test schedule for subsequent Type A tests shall be reviewed an,d approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L,.
a l
Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L., at which time the above test o
schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
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PERRY - UNIT 1 3/4 6-4 Amendment No. 83 I
_ - = =... -..-.-
I PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FRE0VENCY SR 3.6.1.3.9
NOTE-------------------
1 Only required to be met in MODES 1. 2.
l and 3.
1 Verify the combined leakage rate for all
NOTE------
secondary containment bypass leakage SR 3.0.2 is not-paths is s 0.0504 L, when pressurized to applicable
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In accordance l
with 10 CFR 50.
Appendix J. as modified by 1
l approved 1
l exemptions l
SR 3.6.1.3.10
NOTE-------------------
Only required to be met in MODES 1. 2.
and 3.
i Verify leakage rate through each main
NOTE-----
steam line is s 25 scfh when tested at SR 3.0.2 is
= P,.
Until the end of Operating Cycle 6.
not the leakage rate through one main steam applicable i
line is limited to s 35 scfh when tested at = P, as long as the total leakage rate l
througf1allfourmainsteamlinesis In accordance s 100 scfh.
with 10 CFR 50.
Appendix J.
as modified by approved exemptions l
l (continued) l i
i i
i PERRY - UNIT 1 3.6-18 Amendment No. 83 i
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