ML20204E805
| ML20204E805 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/16/1999 |
| From: | Hernan R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20204E811 | List: |
| References | |
| NUDOCS 9903250140 | |
| Download: ML20204E805 (6) | |
Text
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k UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001 44.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 1
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 243 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has founJ that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 6,1995, as supplemented on August 21,1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amendeci (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 1
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.
9903250140 990316 PDR ADOCK 05000327 P
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2.
Accordingly, the license is hereby amended by deleting License Condition 2.C.(23)F of Facility Operating License No. DPR-77.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION 0-MM Cecil O. Thomas, Director Project Directorate 11-3 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Page 11 of License
- Date of issuance: March 16, 1999
- Page 11 is attached for convenience, for the composite license to reflect this change.
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- , c.M D.. Additional Accident Monitorino Instrumentation (Section 22.3, ll.F.f;-
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TVA shall insta'11' interini noble gas munitors at the first cutage' (1) of sufficient duration.
(2)
At the first outage of sufficient duration but no later than startup following the second refueling outage, TVA shall install the following qualified monitoring instrumentation:
(a)
Integrated monitoring assembly which will accomplish g 4-particulate, iodine and noble gas monitoring.
(b) Containment high range radiation monitor.
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c)
Containment pressure monitor.
d)
Containment water level monitor.
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Containment hydrogen monitor.
d..c(c'dE.
Reactor Coolant System Vents (Section 22.3, II.B.1)
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At the first outage of sufficient duration but no later than startup following the second refueling outage, TVA shall install reactor coolant system and reactor vessel head highpoint vents that are remotely operable from the control room.
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Rast Accident sampling (Section 22.3, II.B.3)
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TVA is authorire rate the ins ost Accident Samp1-
-# D D ing System as described in etters dated November 23 and 3 4-g December 21, 1983 ry 9 and 1, ch 23, 1984.
The 6s f-system e operable no later than startup ino the geAe4 refueling outage.
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Instruments of Inadequate Core Cooling (Section 22.3, II.F.2)
(1)
By January l' 1982, TVA shall install a backup indication for ArrtR incore thermocouples.
This display shall be in the control
- /o room and cover the.tenperature range of 200 F - 2000 T.
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(2).
At the first outage of sufficient duration bdt no later than startup following the second refueling outage, TVA shall install Amdy,.
reactor vessel water level instrumentation which meets NRC r9quirements.
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mrade Ecergency Support Facilities '(Section 22.3, ::. A.'.
2)
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(1)
At the first outage of sufficient duration but no lator than startup following the second refueling outage, TVA shall update the Technical Support Facilities to meet NRC requirements.
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(2) TVA shall maintain interim emergency support facilities ! Tech-A#d*'
nical Support Center, Operations Support Center and the imergency M Operations f acility) until the final facilities are c.omplete.
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20065 0001 s+;'...../
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 1
SEQUOYAH NUCLEAR PLANT. UNIT 2 j
AMENDMENT TO FACILITY OPERATING LICENSE l
l Ai.iendment No. 233 I
License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that.
A.
The app lication for amendment by Tennessee Valley Authority (the licensee) dated April 6,1995, as supplemented on August 21,1995, 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.
I 2-
. 2.
Accordingly, the license is horeby amended by deleting License Condition 2.C.(16)g of Facility Operating License No. DPR-79.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y 0-W Cecil O. Thomas, Director Project Directorate ll-3 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Page 7 of License
- k Date of issuance:
March 16, 1999
- Page 7 is attached :u convenience, for the composite license to reflect this change.
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Procedures for Verifying Correct Performance of Operating Activ-ities (Section 22.2, I.C.6)
' Procedures shall be available to verify the adequacy.of the' operating activities.
Control Roo.m Design -(5'ection 5'2.2,1.D.1) d.
TVA shall conside'r the benefits of instailing data recording and Amdh logging equipment in t'.e control room to correct the deficiencies M associatet chart reco! with the trending of important parameters on strip rders used in the control room as part of the Detailed a-/RB3 Control Room Design Review.
in accordance with SECY 82-111B. Implementation shall be carried out Training During Low-Power Testing (Section 22.2,.t.G.1).
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e.
One experienced operator trained on Unit I low power testing for' natural circulation operation shall be assigned to each shift on, this facil'ity.
This requirement shall remain untti TVA submits
- a. report, and NRC agrees with findings, that an acceptable level of training and experience on Unit 2 has been attained.
f.
Reacto'r Coolant System Vents (Section 22.2, II.B.1)
At the first outage of suffici[nt durationi but no later than startup following first refueling outage. TVA shall install reactor coolant system and reactor vessel head highpoint vents that are remotely operable from the control room.
g.
P % cident Sampling (Section 22.2 II.B.3)
' $\\mdk-TVA is authorize te the insta s Accident Sampl-M ing System as described in i
ters dated November ?3 and 3.l(c % i December 21, 198 y 9 and 10 h 23, 1984. The i
system operable no later than startup in9 the QMU j refueling outage.
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h.
Hydrogen Control Measures (Section 22.2, II.B.7)
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s (1) Prior to startup following the first refueling outage, the j
Commission must confirm that an* adequate hydrogen control system for the plant is installed and will perform its intended function in a manner that provides adequate safety
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margins.
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