ML20062L045
| ML20062L045 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/16/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062L047 | List: |
| References | |
| NUDOCS 9312290145 | |
| Download: ML20062L045 (5) | |
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UNITED STATES
,j ;.I,jJi. j NUCLEAR REGULATORY COMMISSION j
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WASHINGTON, D.C. 20555 0001
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 j
BRAIDWOOD STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPi 72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 12, 1993, as supplemented by letters dated November 18 and December 6,1993, 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 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
9312290145 931216 PDR ADOCK 05000456 P
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~ _hnical Specifications (2) 9c t The Technical Specifications contained in Appendix A as revised through Amendment No. 43 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
u<u f. d evf James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation s
Attachment:
Changes to the Technical l
Specifications Date of Issuance:
December 16, 1993 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 43 l
FACILITY OPERATING LICENSE NO. NPF-72 QOCKET NO. STN 50-456 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised page is identified by amendment number'and i
contains vertical lines indicating the area of change.
The page marked with' an asterisk is provided for convenience.
Remove Paaes Insert Paaes 3/4 4-13 3/4 4-13
- 3/4 4-14
- 3/4 4-14 J
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REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENEMTORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable steam generator (s) to OPERABLE status prior to increasing T above 200*F.
y SURVEltlANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of i
Specification 4.0.5."
I 4.4.5.1 Steam Generator Samole Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Samole Selection and inspection - The steam generator tube minimum sample size, inspection result classification, and the
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corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the fre-quencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4 The tubes selected for each inservice inspection shall include at least 3% of the total number F tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas; b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- Unit 1 entered an unplanned outage (AIF26) on October 24, 1993, to repair a tube leak in the IC Steam Generator. The tube leak was less than the reactor-to-secondary leakage limit of Specification 3.4.6.2c for one steam generator. The generator was determined to be OPERABLE following completion of the inspection plan detailed in Letter f SVP/93-063, S. M. Berg, Jr. (Ceco) to J. 7wolinski (NRC), dated November 10, 1993. The generator shall be demonstrated OPERAbtE in accordance with Specification 4.4.5.0 prior to the initial resumption of plant operation following the Unit 1 Cycle 4 Refuel Outage (A1R04).
BRAIDWOOD - UNITS I & 2 3/4 4-13 AMENDMENT NO. 43 w
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1)
All nonplugged tubes that previously had detectable wall penetrations (greater than 20% of wall thickness),
2)
Tubes in those areas where experience has indicated potential problems, and 3)
A tube inspection (pursuant to Specification 4.4.5.4a.8) sN_d be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tuee inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
1)
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and 2)
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are deiraded tubes and none of the inspected tubes are.sefective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (greater than 10% of wall thickness) further wall penetrations to be included in the above percentage calculations.
BRAIDWOOD - UNITS 1 & 2 3/4 4-14 i
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