ML20205E053
| ML20205E053 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/26/1999 |
| From: | Pickett D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205E057 | List: |
| References | |
| NUDOCS 9904050038 | |
| Download: ML20205E053 (6) | |
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1 UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001 FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. NPF-58 1.The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.The application for amendment by the FirstEnergy Nuclear Operating Company (the licensee, formerly The Cleveland Electric illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, OES Nuclear, Inc.,
Pennsylvania Power Company, and Toledo Edison Company) dated September 9,1998, as supplemented by submittals dated January 6, March 4, and March 18,1999, 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 (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 Specifications 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:
9904050038 990326 PDR ADOCK 05000440 p
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'(2) TechnicalSoecifications l
The Technical Specifications contained in Appendix A and the Environmental Protection i
Plan contained in Appendix B, as revised through Amendment No.105 are hereby incorporated into this license. The FirstEnergy Nuclear Operating 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 COMMISSION s
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Douglas V. Pickett, Senior Project Manager l
Project Directorate ill-2 Division of Ucensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance:Nrch 26,1999 9
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ATTACHMENT TO LICENSE AMENDMENT NO.105 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 ;tumber and contain verticallines indicating the area of change.
Remove jnand 3.6-19 3.6-19 5.0-7 5.0-7 5.0-15a 5.0-15a l
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i PCIVs 3.6.1.3 SLRVEILLANCE RE0J1RDMS (continued)
SURVEILLANCC FREQUENCY l
l SR 3.6.1.3.11
NOTES------------------
1.
Only required to be met in MODES 1. 2.
l l
- and 3.
I l
2.
Feedwater lines are excluded.
l Verify combined leakage rate of 1 gpm In accordance i
times the total number of PCIVs through with the hydrostatically tested lines that Primary penetrate the primary containment is not Containment exceeded when these isolation valves are Leakage Rate tested at :t 1.1 P,.
Testing l
Program i
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SR 3.6.1.3.12
.-------------NOTE------------------
l Only required to be met in MODES 1.
l
- 2. and 3.
Verify each outboard 42 inch prirr.ary 18 months containment purge valve is blocked to restrict the valve from opening > 50'.
SR 3.6.1.3.13
NOTE-------------------
Not required to b'e met when the Backup Hydrogen Purge System isolation valves are open for pressure control. ALARA or air l
quality considerations for personnel l
entry, or Surveillances or special testing i
of the Backup hydrogen Purge System that require the valves to be open.
Verify each 2 inch Backup Hydrogen Purge 31 days System isolation valve is closed.
PERRY - LNIT 1 3.6-19 Aioeoit No. 105 l
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Programs and Manuals 5.5 1
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5.5 Programs and Manuak
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l 5.5.1 Offsite Dose Calculation Manual (0DCM).(continued) c.
Chall be submitted to the NRC in the form of a complete.
legible co) with, the ;y cf the entire ODCM as a part of. or concurrent l
ac4; active Effluent Release Report for the period l-of the report in which any change in the ODCM was made.
Each change shall be identified by markings in the margin of i
the affected pages, clearly indicating the area of the page l
that was chm ged, and shall indicate the date (i.e.. month and year) the change was iinplemented.
r 5.5.2 Primary Coolant Sources Outside Containment 1
l This progran provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to l
levels as low as practicable. The systems include the Low Pressure Core Spray System. High Pressure Core Spr6y System.
Residual Heat Removal System. Reactor Core Isolation Cooling System, hydrogen analyzer portion of the Combustible Gas Control System. Post-Accident Sampling System. Reactor Water Cleanup l
System Return to Feedwater line, and Feedwater Leakage Control System including the Feedwater System motor-o>erated containment isolation valves. The program shall include tie following:
a.
Preventive maintenance and periodic visual inspection l
requirements: and b.
Integrated leak test reguirements for each system at I
l refueling cycle intervals or less.
5.5.3 Post Accident Samolino This program provides controls tbt ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosp'aere samples undar accident conditions. The program shall include the l
following:
a.
Training of personnel:
b.
Procedures for sampling and analysis: and c.
Provisions for mainocnar.ce of sampling and ana'ysis l
equipment.
(continue'dl FERRY - WIT 1 5.0-7 kedad. No.105 ayr
Programs and Manu'ils i
f.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakaae Rate Testina Procram (continued)
BN-TOP-1 methodology may be used for Type A tests.
The corrections to NEI 94-01 which are identified on the crrata Sheet attached to the NEI letter. "A>pendix J Workshop Questions and Answers." dated Marc1 19. 1996, are considered an integral part of NEI 94-01.
The contalument isolation check valves in the Feedwater enetrations are tested per the Inservice Testing Program p(Technical Specification 5.5.6).
The peak calculated primary containment internal pressure for the design basis loss of coolant accident P., is 7.80 psig.
The maximum allowable primary containment leakage rate. L., shall be 0.20% of primary containment air wei t calculated peak containment pressure (P. per day at the Leakage rate acceptance criteria are:
a.
Primary containment leakage rate acceptance criterion is s 1.0 L. However, during 13 e first unit startup following testing, performed in accori.1ce with this Program, the leakage rate acceptance criteria are < 0.6 L for the Type B and Type C tests, and s 0.75 L, for the Type,A tests; b.
Air lock testing acceptance criteria are:
1) 0verall air lock leakage rate is s 2.5 scfh when tested at a P..
2)
For each door. leakage rate is s 2.5 scfh when the gap between the door seals is pressurized to a P,.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
PERRY - LNIT 1 5.0-15a Mernient No.105
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