ML20234A959
| ML20234A959 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/09/1987 |
| From: | Zwolinski J NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20234A961 | List: |
| References | |
| NUDOCS 8709180211 | |
| Download: ML20234A959 (14) | |
Text
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1 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. DPR-77 1.
The Nuclear Reculetory Comission (the Lomission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the 1
licensee)datedApril 14, 1987, clarified on July 8,1987 and July 27, 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 set forth in 10 CFR Chapter I; 8.
The facility will operc h in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 i
of the Comission's regulations and all applicable requirements have been satisfied.
i DR ADO PDR P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and 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 1
revised through Amendment No. 57, are hereby incorporated in the license. The lice.nsee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fe
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4.h 1 A. Zwolinski sistant D rector j
m f3r Projects v
TVMProjectsDivision Vfice of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: September 9, 1987 l
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-ATTACHMENT TO LICENSE AMENDMENT N0. 57 FACILITY OPERATING LICENSE N0. DPR-77 DOCKET N0. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by.the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3-72 3-72 3-72a 3-72a*
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TABLE 4.3-8 (Continued) l l
TABLE NOTATION
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~During liquid additions to the tank.
l
-(1) The CHANNEL-FUNCTIONAL TEST shall-also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the l
following conditions exists:
1 1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Downscale failure.
l (2) The CHANNEL FUNCTIONAL TEST.shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
]
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Downscale failure.
l (3) The. initial CHANNEL CALIBRATION shall be performed using one or more of i
the reference standards certified-by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRM~ ION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least onca per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isola-tion of this pathway and control room alarm annunciation occurs if any of the following conditions occur:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs:
1.
Downscale failure.
SEQUOYAH - UNIT 1 3/4 3-73 Amendment No. M, 57
INSTRUMENTATION RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.
APPLICABILITY:
As shown in Table 3.3-13 ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation chan-nel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gas-eous effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservative.
l b.
With less than the minimum number of radioactive gaseous effluent monitorice instrumentation channels OPERABLE, take the ACTION shown-in Table 3.3-13.
Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-Annual Rad'9 active Effluent Release Report why the opera-bility could not be corrected within 30 days.
c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.
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SEQUOYAH - UNIT 1 3/4 3-74 Amendment No. 42 l
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TENNESSEE VALLEY AUTHORITY 1
1 DOCKET N0. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.49.
License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 14, 1987 clarified on July 8,1987 and July 27, 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 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; C.
There is reasonable assurance (1) that the. activities authorized by this amendment can be conducted without endangering the heelth 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 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 Comission's regulations and all applicable requirements have been satisfied, l
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
& ['
"'W J n
\\. Zwolinski, ss stan rector fo Projects VA, rojects Division Office of Special Projects
Attachment:
Changes to the Technical Speci fications -
Date of Issuance: September 9, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 49 h
FACILITY OPERATING LICENSE NO. DPR-79 DOCKET N0. 50-328 l
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3-73 3-73 3-74 3-74*
3-75 3-75 3-76 3-76*
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TABLE 4.3-8-(Continued)
TABLE NOTATION J
During liquid additions to the tank.
l (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if-any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip'setpoint, i
2.
Circuit failure.
l 3.
Downscale failure.
1 i;
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room
]
alarm annunciation occurs if any of the following conditions exists:
(
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Downscale failure.
j (3) The initial CHANNEL CALIBRATION shall b'e performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall-permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration'shall be used.
(4) CHANNELCHECKshallconsistofverifyingindicationofflowduribgperiods of release.
CHANNEL CHECK shall be made at least once per.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and a control room annunciation occurs if any of the follow '
ing conditions occur:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
j 2.
Circuit failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs:
1.
Downscale failure.
l 1
SEQUOYAH - UNIT 2 3/4 3-75 AmendmentNo./,49 i
' INSTRUMENTATION RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.
APPLICABILITY:
As shown in Table 3.3-13 ACTION.
a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Spe-cification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive gaseous effluent 1
monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3'13.
Exert best efforts to return the instrument to OPERABLE' status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the opera-bility could not be corrected within 30 days, c.
The provisio~ns of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not j
applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERA'BLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9.
I I
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SEQUOYAH - UNIT 2 3/4 3-76 Amendment No. 34 (Corrected page) 2-20-86