ML20034H724
| ML20034H724 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/12/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034H721 | List: |
| References | |
| NUDOCS 9303190327 | |
| Download: ML20034H724 (5) | |
Text
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'o UNITED STATES
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g NUCLEAR REGUL ATORY COMMISSION 7;
E WASHING TON, D. C. 20555
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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. DPR-40 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated October 9, 1992, 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 CFl' Chapter I; B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D.
The issuance of this license 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.
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9303190327 930312 DR -ADOCK 0500 5;
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Accordingly, facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. ~ 150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 60 days from date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION T
George T. Hubbard, Acting Director Project Directorate IV-1.
Division of Reactor Projects - III/IV/V Office of Nuclear Reactor ~ Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 12, 1993 t
t'
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e' ATTACHMENT TO LICENSE AMENDMENT NO.150 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET N0; 50-285 i
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Revise. Appendix "A' Technical Specifications as indicated below. The revised I
pages are-identified by amendment number and contain vertical lines indicating the area of change.
i REMOVE PAGES INSERT PAGES 2-34 2-34 2-35 2-35 s
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+
I i
F F
E i
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2.0-LIMITING CO@1TIONS FOR OPERATION c
2.7 Electrical Systez (Continued)
^
d.
Either one of the 4.16kV engineered safeguards buses, I A3 or 1 A4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the operability of the diesel generator associated with the operable bus is demonstrated immediately and there are no inoperable engineered safeguards components associated with the operable bus.
)
e.
One of each group of 4160 V/480 V Transformers (T1B-3A or 4A),
(T1B-3B or 4B), and (TIB-3C or 4C) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable engineered safeguards components which
{
are redundant to components an the inoperable transformer.
j f.
One of the 480 V distribution buses connected to bus lA3 or connected to bus IA4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on the inoperable bus.
1 g.
Either Group of MCC No.'s (3A1,3B1,3A2,3Cl,3C2,) or (4A1,4A2, 4Cl, 4C2) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on the inoperable MCC. MCC 3Cl may be inoperable in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> f
if battery chargers No. I and No. 2 are operable.
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h.
One of the four 120V a-c instrument buses (A, B, C or D) may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the reactor protective and engineered l
safeguards systems instrument channels supplied by the remaining three buses are all operable.
i.
Two battery chargers may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided I
battery charger No.1 (EE-8C) or No. 2 (EE-8D) is operable.
j.
Either one of the emergency diesel generators (DG-1 or DG-2) may be inoperable for up to seven days (total for both) during any month, provided there are no inoperable engineered safeguards components associated with the operable diesel generator. If one diesel generator is l
inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (regardless of when the inoperable diesel generator is restored to operability) EITHER:
(1)
Start the other diesel generator to verify operability, OR (2)
Ensure the absence of common cause for the diesel generator inoperability for the other diesel generator.
2-34 Amendment No. 60,147, 150 mm
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2.0 LIMITING CONDITIONS FOR OPERATION 2.7 Electrical Systems (Continued)
I k.
Island buses IB3A-4 A, IB3B-4B, and IB3C-4C may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable safeguards components which are redundant to components on the inoperable bus (es).
1.
Either one of the 125V d-c buses No.1 or 2 (Panels EE-8F or EE-8G) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
m.
Either one of the 125V d-c distribution panels AI-41A and AI-41B may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
n.
Either one of the 120V a-c instrument panels Al-42A or AI-42B may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Basis The electrical system equipment is arranged so that no single failure can inactivate enough engineered safeguards to jeopardize the plant safe.,,. The 480 V safeguards are arranged on nine bus sections. The 4.16 kV safeguards are supplied from two buses.
The normal source of auxiliary power with the plant at power for the safeguards buses is from the house service power transformers being fed from the 161 Kv incoming line with on-site emergency power from either one of two diesel generators and off-site standby power via the unit auxiliay transformers.* The loss of the 161kV incoming line renders the house service transformers (TIA-3 and TIA-4) inoperable in that the transformers cannot supply power to the 4.16kV safeguards buses IA3 and 1 A4.
Inoperability of the house sen' ice transformer (s) or loss of the 161kV incoming line is not reportable pursuant to 10 CFR 50.72 criteria; however, the NRC will be promptly notified of these events via the NRC Operations Center.
The two emergency diesel generators on site do not require outside power for start up or operation.
Upon loss of normal and standby power sources, the 4.16 Ky buses I A3 and 1 A4 are energized from the diesel generators. Bus load shedding, transfer to the diesel generator and pickup of critical loads are carried out automatically.*
When the turbine generator is out of service for an extended period, the generator can be isolated by opening motor operated disconnect switch DS-Tl in the 'vas between the generator and the main transformer, allowing the main transformer and the unit auxiliary power transformers (TI A-1 and TI A-2) to be returned to service.* The auxiliary power transformers are not considered inoperable during these normal plant startup/ shutdown realignments.
2-35 Amendment No. gf
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