ML20205F606
| ML20205F606 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/24/1987 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205F610 | List: |
| References | |
| NUDOCS 8703310214 | |
| Download: ML20205F606 (8) | |
Text
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UNITED STATES o
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NUCLEAR REEULATORY COMMISSION p
WASHINGTON, D. C. 20555
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DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment-to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated February 17, 1986, and supplemented February 5 and March 16, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the oublic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l{
of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby arrended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.69, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specitications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COINISSION
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Darl Hood, Project Panager PPR Project Directorate #4 Division of PWR Licensing-A Attachtrent:
Technical Specification Charges Date of Issuance: March 24, 1987 DSIf hG PWR#4/Dk'WR-A PWR#4/DPWR-A FOB /DPUR-A 0 /f;ET -
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UNITED STATES p-NUCLEAR REGULATORY COMMISSION o
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i DUKE POWER COMPANY 00CKET N0. 50-370 McCUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.50 License No. NFF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment ~to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated February 17, 1986, and suppleinented February 5 and March 16, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; 8
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; i
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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and sa'fety of the oublic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all apolIcaale requirements have been satisfied.
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I 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Focility Operating License No. NPF-17 is hereby arnended to read as follows:
(2) Techr.ical Specifications The Technical Specifications contained in Appendix'A, as revised through Amendment No.50, are bereby incorporated into the 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 its date of issuance.
FOR TliE hUCLEAR PELULATORY COFNISSION
\\9 Darl Hood, Project Fianacer FWR Project Directorate #4 Division of PWR Licensing-A Attachr'cnt:
Technical Specification Changes Date of Issuance:
March 24, 1987 MIturi an:rrac DHood VPenaroya GdMV D
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o ATTACH!1EliT TO LICENSE AMENDitEf;T f:0. 69 fl.CILITY OPERATING LICENSE f!0. I;PF-9 4
DOCKET f;0. 50-369 AND TO LICENSE AltEf;DMENT NO. 50 FACILITY OPERAT!?;G LICEhSE f'O. f:rF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Tectricel Frecifications with
- he enclosed pages.
The revirrd rcges are identified by Amendnent nur.ber and cer.ttin sertical lines indicating the areas of change.
/ciended Page 3/4 9-16 3/4 9-17 B3/4 9-3
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REFUELING OPERATIONS 3/4.9.12 FUEL STORAGE - SPENT FUEL STORAGE POOL c
LIMITING CONDITION FOR OPERATION 3.9.12 Fuel is to be stored in the spent storage pool with:
a.
The baron concentration in the spent fuel pool maintained at greater than or equal to 2000 ppm; and b.
Storage in Region 2 restricted to irradiated fuel which has deceyed at least 16 days and one of the following:
1) fuel which has been qualified in accordance with Table 3.9-1; or 2)
Fuel which has been qualified by means of an analysis using NRC approved methodology to assure with a 95 percent probability at a 95 percent confidence level that k,ff is no greater than 0.95 including all uncertainties; or 3)
Unqualified fuel stored in a checkerboard configuration.
In the' event checkerboard storage is used, one row between normal storage locations and checkerboard storage locations will be vacant.
APPLICABILITY:
During storage of fuel in the spent fuel pool.
ACTION:
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a.
Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined a fuel assembly has been placed in the incorrect Region until such time as the correct storage location is determined.
Move the assembly to its correct location before resumption of any other fuel movement.
b.
Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined the pool boron concentration is less than 2000 ppm, until such time as the boron concentration is increased to 2000 ppm or greater.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12a. Verify all fuel assemblies to be placed in Region 2 of the spent fuel pool are within the enrichment and burnup limits of Table 3.9-1 or that k,ff < 0.95 by checking the assemblies' design and burnup documentation or the assemblies' qualifying analysis documentation respectively.
b.
Verify at least once per 31 days that the spent fuel pool boron con-centration is greater than 2000 ppm.
Amendment No. 69 Unit 2 McGUIRE - UNITS 1 and 2 3/4 9-16 Amendment No. 50 Unit 1
Table 3.9-1 Minimus Burnup Vers ~us Initial Enrichment for Region 2 Storage Initial Enrichment Assembly Burnup w/o U-235 (GWD/MT) 1.4................................................... 0.00 1.5................................................... 2.50 1.6...................................................
5.00 1.7...................................................
6.65 1.8...................................................
8.30 1.9...................................................
9.95 2.0..................................................
11.60 2.1..................................................
13.20 2.2..................................................
14.60 2.3..................................................
16.00 2.4..................................................
17.40 2.5..................................................
18.80 2.6..................................................
20.20 2.7....j.............................................
21.40 2.8..................................................
22.60 2.9..................................................
23.90 3.0..................................................
25.20 3.1..................................................
26.60 3.2..................................................
27.80 3.3..................................................
28.93 3.4..................................................
30.07 3.5..................................................
31.20 s
3.6..................................................
32.26 3.7..................................................
33.32 3.8..................................................
34.38 3.9..................................................
35.44 4.0..................................................
36.50 Amendment No. 69 (Unit 1)
McGUIRE - UNITS 1 and 2 3/4 9-17 Amendment No. 50 (Unit 2)
BASES l
3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM The limitations on the Fuel Handling Ventilation Exhaust System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
The methyl iodide penetration test criteria for the carbon samples have been made more restrictive than required for the assumed iodine removal in the accident analysis because the humidity to be seen by the charcoal adsorbers may be greater thart 70% under normal operating conditions.
3/4.9.12 FUEL STORAGE - SPENT FUEL STORAGE POOL The requirements for fuel storage in the spent fuel pool on 3.9.12 (a) and (b) ensure that:
(1) the spent fuel pool will remain subcritical during fuel storage; and (2) a uniform boron concentration is maintained in the water volume in the spent fuel pool for reactivity control. The value of 0.95 or 1ess for Keff which includes all uncertainties at the 95/95 probability /
confidence level as described in Section 9.1.2.3.1 of the FSAR is the accept-ance criteria for fuel storage in the spent fuel pool.
Table 3.9-1 is con-servatively developed in accordance with the acceptance criteria and methodology referenced in Section 5.6 of the Technical Specifications.
Storage in a checker-board configuration in Region 2 meets all the acceptance criteria referenced in Section 5.6 of the Technical Specifications and is verified in a semi-annual basis after initial verification through administrative controls.
The Action Statement applicable to fuel storage in the spent fuel pool ensures that:
(1) the spent fuel pool is protected from distortion in the fuel storage pattern that could result in a critical array during the movement of fuel; and (2) the boron concentration is maintained at 2000 ppm during all actions involv-ing movement of fuel in the spent fuel pool.
The Surveillance Requirements applicable to fuel storage in the spent fuel pool ensure that:
(1) fuel stored in Region 2 meets the enrichment and burnup limits of Table 3.9-1 or the K,ff 1 0.95 acceptance criteria of an analysis using NRC approved methodology; and (2) the boron concentration meets the 2000 ppm limit.
McGUIRE - UNITS 1 and 2 B 3/4 9-3 Amendment No.69(Unit 1)
Amendment No.50(Unit 2)