ML16138A809
| ML16138A809 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/02/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16138A810 | List: |
| References | |
| NUDOCS 9604080216 | |
| Download: ML16138A809 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. DPR-38
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated April 2, 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 as 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 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 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
9604080216 960402 PDR ADOCK 05000269 P
-PDR
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.215, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION H bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 2, 1996
PtREG&4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. DPR-47
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated April 2, 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 as 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 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 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.215, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 2, 1996
o\\9gI REG(10 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-M001 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. DPR-55
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated April 2, 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 as 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 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 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.212, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR HE NUCLEAR REGULATORY COMMISSION Her ert N. Berkow, Director Pr ject Directorate 11-2 Division of Reactor Projects -
I/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 2, 1996
ATTACHMENT TO LICENSE AMENDMENT NO.215 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO.
215 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 212 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages 4.5-8 4.5-8 4.14-1 4.14-1 4.14-2 4.14-2
0
- e.
During each refueling outage, following 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation, or after painting, fire, or chemical release in any ventilation zone communicating with the system, a carbon sample shall be removed from the Penetration Room Ventilation system filters for laboratory analysis. Within 31 days of removal, this sample shall be verified to show 290% radioactive methyl iodide removal when tested in accordance with ASTM D3803-1989 (30*C, 95% R.H.). Otherwise, the filter system shall be declared inoperable.
Ban Pressure drop across the combined high efficiency particulate air (HEPA) filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter. A test frequency of once per year operating cycle establishes performance capability.
(HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential release of radiolodine.
Bypass leakage for the charcoal adsorbers and particulate removal efficiency for HEPA filters are determined by halogenated hydrocarbon and DOP respectively. The laboratory carbon sample test results indicate a radioactive methyl iodide removal efficiency for expected accident conditions. Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers. If the performances are as specified, the calculated doses would be less than the guidelines stated in 10 CPR 100 for the accidents analyzed.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated, Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52. The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be replaced. Any HEPA filters found defective should be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
Operation of the system every month will demonstrate operability of the filters and adsorber system. Operation for 15 minutes demonstrates operability and minimizes the moinure build up during testing.
If painting, fire or chemical release occurs during system operation such that the HEPA filter or charcoa! adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sample analysis should be performed as required for operational use.
Demonstration of the automatic initiation capability is necessary to assure system performance capability, Oconee Units 1, 2 and 3 Amendment No. 215 Amendmerit No. 215 Amendment No. 212
4.14 REACTOR BUILDING PURGE FILTERS AND SPENT FUEL POOL VENTILATION SYSTEM Applies to testing of the Reactor Building purge filters for Units 2 and 3 and the spent fuel pool ventilation systems.
Objective To verify that the Unk 2 and Unit 3 Reactor Building purge filters will per-form their design fnction and that when used with the spent fuel pool ventilation system, will reduce the off-site dose due to a fuel handling accident.
Spiflcainn 4.14.1 Operational and Performance Testing
- a.
Monthly, each train of the spent fuel pool ventilation system shall be operated through the respective Reactor Building purge filters for at least 15 minutes at design flow +/- 10%.
- b.
During each refueling outage, the spent fuel pool ventilation fans shall be 6own to operate at deign flow -t 10% when tested in aucordance with ANSI NS10-1975.
- c.
Leak tests using DOP or halogenated hydrocarbon. as appropriate shall be performed on the Reactor Building purge filters.
- 1.
During each refueling outage;
- 2.
After each complete or partial replacement of HEPA filter bank or charcoal adsorber bank;
- 3.
After any structural maintenance on the system housing;
- 4.
After painting, fire, or Chemical release in any ventilation zone communicadng with the system.
- d.
The results of the DOP and halogenaled hydrocarbon tests on HEPA filters and charcoal adsorber banks shall show > 99% DOP removal and > 99%
halogenated hydrocarbon removal, respectively, when teated in accordance with ANSI NS10-1975.
Owuee 1. 2 and 3 Amendment No.
215 Amendment No. 215 4.14-1 Amendment No.
212
- e.
During each sfucling outagc, following 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation, or after painting, fire, or chemical release in any ventilation zone communcating with the system, a carbon sample shall be removed from the Reactor Building purge filters for laboratory analysis. Within 31 days of removal, this sample shall be verified to show >_ 90% radioactive methyl Iodide removal when tested in accordance with ASTM D3803-1989 (30C, 95% R.H.). Otherwise, the filter system shall be declared Inoperable.
The Unit 2 Reactor Building purge filter is used in the venilation system for the common spent ftel pool for Units 1 and 2. The Unit 3 Reactor Building Purge filter is used in the Unit 3 spent fuel pool ventilation system. Each filter is constructed with a prefilter, an absolute filter and a charcoal filter in series, The high efficiency particulate air (HEPA) filters are installed before the charcoal adsorbere to prevent clogging of the iodine adsorbers. The charcoal adsorbors are Installed to reduce the potential release of radiolodine.
Bypass leakage for the charcoal adsorbers and particulate removal efficiency for HEPA filters are determined by halogenated hydrocarbon and DOP respectively. The laboratory carbon sample test results Indicate a radioactive methyl Iodide removal efficiency for expected accident conditions. Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers. If the performances are as specified, the doses for a fuel handling accident would be minimized.
The frequency of tests and sample analysis are ncessary to show that the HEPA filters and charcoal adsorberS cA perform as evaluated. Replacement adsorbent should be qualied according to the guidelines of Regulatory Guide 1.52. The charcoal adsorbar efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples. Each sample should be replaced. Any HEPA filters found defective should be replaced with filters qualgned pursuant to Rcgulatory Position C.3.d of Regulawry Guide 1.52, Operation Of the spent f e pool ventilation system every month will demonstrate operability of t
fans, filters and adsorber system, If Painting. fire or chemical releae occurs during system operaton such that the IPA filter or charcoal adsorber could become contaminated from the thos, chemicals or foreign atr'als, a same tests and sample analysis should be performod as required for operational use.
Oconee 1, 2, and 3 Amendment No. 215 Amendment No. 215 4.14-2 Amendment No. 212