ML20079P810
| ML20079P810 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/18/1991 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P812 | List: |
| References | |
| NUDOCS 9111140065 | |
| Download: ML20079P810 (8) | |
Text
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' NUCLEAR REGULATORY COMMISSION I c.
WASHINGTON, D. C. 20555
%,:.....f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327.
SE000YAH_ NUCLEAR PLANT, UNIT 1 AltENDfTpT_T0_FACILITYOPERATINGLICENSE
/rendment flo.154-License No. DPR-77
- 1. -
The Nuclear Regulatory Connissior, (the Commission)-has found that:
A, The applicatien for amendment by Tennessee Valley Authority (the licensee) dated October 11, 1991,' 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 authori7.ed 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 comon defense rind security or. to the health and safety of the public; and E.
The issuance of this amendment is in accordarce with 10-CFR Part 51 of.the_ Commission's regulations and-all applicable requirements have
..been satisfied.
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2.
Accordingly, the license is ancoded by changes to the Technical Specifications as indicated in the attachment to this license amendment ar.d paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Araendment No.154, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specificctions.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMillSS10N f)-
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Gus C. Lainas, Assistant Director for Region 11 Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachrent:
Changes to the Technical Specifications Date of Issuance: October 18, 1991 M
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s ATTACH!tEtiT TO LICENSE AltEtREtiT t:0. 154 FAClllTY OPERATitlG L10EllSE iT. DPR-77 DOCKET t:0, 50-3H Revise the Appendix A Tectnical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captiored amendrent nunber and contain rarginal lines indicating the area of change.
REMOVE INSERT 3/4 8-4 3/4 8-4 l
______________________.____________________-_________________________-______x
)
4 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in con. junction with its manufacturer's recommendations for this class of standby service, 2.
Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage within i 10 percent of the initial pretest voltage and frequency at 60 + 1.2 Hz.
At no time shall the transient voltage exceed 8276V.
3.
Verifying the generator capability to reject a load of 4400 kw without tripping.
The generator voltage shall not exceed 120 percent of the initial pretest voltage or 8712V, whichever l
is less during and following the load rejection.
4.
Simulating a loss of offsite power by itself, and:
a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown boards, b)
Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.
After energization, the steady state voltage and frequency of the shutdown boards shall be maintained at 6900 690 volts and 60 1 1.2 Hz during this test.
5.
Verifying that on a ESF actuation test signal (without loss of off3ite power) the diesel generator starts on tbo auto-start signal and operates on standby for greater than or equal to 5 minutes.
The generator voltage and frequency shall be 6900 690 volts and 60 1.2 Hz within 10 seconds after the auto-start signal; tne steady state generator voltage and fre-quency shall be maintained within tnese limits during this test.
6.
Simulating a loss of offsite power in conjunction with an ESF actuation test signal, and a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown bo&rds, b)
Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.
After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 6900 690 volts and 60 ! 1.2 Hz during this test.
SEQUOYAH - UNIT 1 3/4 8-4 Amend.nent No. 49, 64, 114, 137 154
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-3?8 SEQUOYAH NUCLEAR PLANT, UNIT,2 AMENDMENT TO FACILITY OPERATING LICENSE Amencrrent No.144 License No. DPR-79
- 1.
The Huclear Regulatory Cnmission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 11, 1991, complies with the standards and
-requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission; -
I 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon
-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 tbo Comission's regulations and all applicable requirements have -
-been satisfied.
'-~ '
+
a
1 s 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license ar.iendment and paragraph 2.C,(2) of f acility Operatino License No. DPR-79 is hereby amended to re6c as follows:
(2) Technical Specifications The Technical Specifications ccntained in Appendices A and B, as revised thrcugh Amendr.ent No.144, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of its date of issuance.
FOR TifE NUCLEAR REGULATORY COMiiISSION 7
,h.
w Gus C. Lainas, Assistant Director for Region II Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 18, 1991 n
1 s
ATTACHMENT _TO LICENSC AMENOMENT NO.144 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET 00. 50-328 Revise the Appendix t. Technical Specifications by removing the pages identified below ar.d inserting the enclosed pagas. The revised pages are identifits by tite (aptioned ar.endnent number and contain trarginal lines indicatirg the area of change.
REMOVE _
INSERT 3/4 8-4 3/4 8-4
~.
1 l
s ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspectior, in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, 2.
Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage at within i 10 percent of the initial pretest voltage and frequency at 60 + 1.2 Hz.
At no time shall the transient voltage exceed 8275V.
3.
Verifying the generator capability to reject a load of 4400 kw without tripping.
The generator voltage shall not exceed 120 percent of the initial pretest voltage or 8712V, whichever l
is less during and following the load rejection.
4.
Simulating a loss of offsite power by itself, and:
a)
Verifying de energization of the shutdown boards and load shedding from ti.e shutdown boards.
b)
Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.
After energization, the steady state voltage and frequency of the shutdown boards shall be maintained at 6900 690 volts and 60 1.2 Hz during this test.
5.
Verifying that on a ESF actuation test signal, without loss of offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.
The generator voltage and frequency shall be 6900 1 690 volts and 60 t 1.2 Hz within 10 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained within these limits during this test.
6.
Simulating a loss of offsite power in conjunction with an ESF actuation test signal, and a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.
b)
Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.
After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 6900 690 volts and 60 1.2 Hz during this test.
SEQUOYAH - UNIT 2 3/4 8-4 Amendment No. 41,123 144
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