ML20069G891
| ML20069G891 | |
| Person / Time | |
|---|---|
| Site: | Perry  (NPF-58-A-060, NPF-58-A-60) |
| Issue date: | 05/26/1994 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069G894 | List: |
| References | |
| NUDOCS 9406100210 | |
| Download: ML20069G891 (7) | |
Text
__.
=
pentou g..
., S S
UNITED STATES
.'5^
NUCLEAR REGULATORY COMMISSION
- (-
,/
WASHINGTON, D.C. 20555 @ 01 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
)
DOCKET NO. 50-440 I
PERRY NUCLEAR POWER PLANT. UNIT NO. I t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 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, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated March 1, 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 confarmity 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 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 Operating License No. NPF-58 is hereby amended to read as follows:
9406100210 940526 PDR ADOCK 05000440 P.
1
. (2) Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised thrcugh Amendment No. 60 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.
l FOR THE NUCLEAR REGULATORY COMMISSION W
Jon B. Hopkins, Sen or Project Manager Project Directorate III-3' Division of Reactor Projects III/IV.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of issuance:
May 26, 1994 I
I
ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications 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 3/4 10-1 3/4 10-1 5
m
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or equal to 0.75 L.,*
a.
where L is 0 per 24 bours.20 percent by weight of the primary containment air at P,.
A combined leakage rate of less than or equal to 0.60 L, isolation b.
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 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,.
l APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, AND 3, with the reactor coolant system temperature greater than 200 *F.
ACTION:
With:
a.
The measured overall integrated primary containment leakage rate 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 8 and C tests exceeding 0.60 L,, or c.
The measured leakage rate exceeding 25 scf per hour for any one main steam line through the isolation valv_es, or d.
The combined leakage rate for all penetrations that are secondary 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 primary containment exceeding 1 gpm times the total number of such valves:
Restore the leakage rate to less than or equal to the above limit (s) within 1 i
hour or be in at least HOT SHUTDOWN within the next 12,. hours and in COLD i
SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
PERRY - UNIT 1 3/4 6-3 Amendment No. AA/07,60
t CONTAINMENT SYSTEMS F
SURVElllANCE RE0VIREMENTS
[
t 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972 and BN-TOP-1; test results shall also be reported based on the Mass Point Methodology described in ANSI /ANS N56.8-1981:
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall l
be conducted at 40-10 month intervals during shutdown at P during i
each 10-year %e vice period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice i
inspection.
b.
If any periodic Type A test fails to meet 0.75 L the test schedule l
forsubsequentTypeAtestsshallbereviewedand,approvedbythe Commission.
If two consecutive Type A tests fail to meet 0.75 L, a e
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
}
schadule may be resumed.
c.
The accuracy -of each Type A test shall be verified by a supplemental I
test which:
j t
i i
l i
1 I
1 1
PERRY - UNIT 1 3/4 6-4 Amendment N,0. ff,f/,60 1
i
,.7,..
i,h 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY /DRYWELL INTE3RITY LIMITING CONDITION FOR OPERATION 3.10.1 The provisions of Specifications 3.6.1.1.1, 3.6.1.3, 3.6.2.1, 3.6.2.3, 3.6.5.1, 3.6.5.2, 3.9.1 and 3.9.3 and Table 1.2 may be suspended to permit the reactor pressure vessel closure head and the drywell head to be removed and the drywell air lock door to be open when the reactor mode switch is.in the Startup position during low power PHYSICS TESTS with THERMAL POWER less than 1% of RATED THERMAL POWER and reactor coolant temperature less than 200*F.
APPLICABILITY: OPERATIONAL CONDITIONS 2 and 5, during low power PHYSICS TESTS or shutdown margin demonstrations.
ACTION:
With THERMAL POWER greater than or equal to 1% of. RATED THERMAL POWER or witn the reactor coolant temperature greater than or equal to 200*F, immediately place the reactor mode switch in the Shutdown position.
SURVEILLANCE RE0VIREMENTS 4.10.1 The THERMAL POWER and reactor coolant temperature shall be verified to be within the limits at least once per hour during low power PHYSICS TESTS or shutdown margin demonstrations.
PERRY - UNIT 1 3/4 10-1 Amendment No. 60
SPECIAL TEST EXCEPTIONS 3/4.10.2 ROD PATTERN CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.10.2 The sequence constraints imposed on control rod groups by the rod pattern control system (RPCS) per Specification 3.1.4.2 may be suspended by means of the individual rod position bypass switches for the following tests:
a.
Shutdown margin demonstrations, Specification 4.1.1.
b.
Control rod scram insertion times, Specification 4.1.3.2.
c.
Control rod friction measurements.
d.
Startup Test Program with the THERMAL POWER less than the RPCS low power setpoint.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With the requirements of the above specification not satisfied, verify that the RPCS is OPERABLE per Specification 3.1.4.2.
SURVEILLANCE REQUIREMENTS 4.10.2 When the sequence constraints imposed on control rod groups by the RPCS are bypassed, verify:
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to bypassing any sequence constraint and at a.
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while any sequence constraint is bypassed, that movement of the control rods between 75% ROD DENSITY to the RPCS low power setpoint is limited to the established control rod sequence for the specified test, and b.
Conformance with this specification and test procedures by a second licensed operator or other technically qualified member of the unit technical staff.
- ~
c P
o
.ew s PERRY - UNIT 1 3/4 10-2