ML20211N881
| ML20211N881 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/07/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211N886 | List: |
| References | |
| NUDOCS 9909130098 | |
| Download: ML20211N881 (12) | |
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 49.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 245 License No. DPR-77
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 15,1999, 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 J
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
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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.
9909130098 990907 PDR ADOCK 05000327 P
PDR J
. 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 revised through Amendment No.
245, 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, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-, )\\% b h.d w Sheri R. Peterson, Chief, Section 2 Project Directorate il Division of Licensing Project Management -
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 7, 1999 I
i
ATTACHMENT TO LICENSE AMENDMENT NO. 245 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below ano inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginallines indicating the area of change-.
REMOVE INSERT Index Page V Index Page V 3/4344 3/4344 3/4345 3/4 3-46 B 3/4 3-3 8 3/4 3-3
-7 i EP i
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LIMITING CONDITIONS FOR OPERATTON AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1
' AXIAL FLUX DIFFERENCE (AFD) 3/4 2-1 3/4.2.2 HEAT FLUX ' HOT CHANNEL FACTOR-FQ (Z)..
. 3/42 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.
3/4 2-10 R142 3/4.2.4 QUADRANT PO* DER TILT RATIO.
3/4 2-12 3/4.2.5 DNB PARAMETERS 3/4 2-15 i
l i
3/4.3 INSTPUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 q
3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 3/4 3-39
. MOVABLE INCORE DETECTORS 3/4 3-43 SEISMIC-INSTRUMENTATION (DELETED) 3/4 3-44 l
METEOROLOGICAL INSTRUMENTATION 3/4 3-47 3/4 3-50 REMOTE'SHUTDONN INSTRUMENTATION CHLORINE DETECTION SYSTEMS (DELETED) 3/4 3-54 1
3/4 3-55 ACCIDENT MONITORING INSTRUMENTATION FIRE DETECTION INSTRUMENTATION (DELETED) 3/4 3-58 lR231 j
......3/4.3-70 DELETED R152 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-71 SEQUOYAH - UNIT 1 V
Amendment No. 62, 138, 148, 227,245
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' INSTRUMENTATION SEISMIC INSTRUMENTATION JLIMITING CONDITION FOR OPERATION.
3.3.3.3 This specification is deleted.
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(Pages 3/4 3-44 through 3/4 3-46 are deleted) l l
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SEQUOYAH ; UNIT 1 3/4 3-44 Amendment No. 12, 81, 213, 245
E INSTPUNENTATION BASES 3/4.3.3.3 SEISMIC INSTRUMENTATION This specification is deleted.
l 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteoro]ogical data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating pro *ective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 PEMOTE NIIUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT BR STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control rocm.
This capability is required in the event control room habitability is lost and la consistent with General Design Criterion 19 of 10 CFR 50 3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
R66 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2,
" Instrumentation R153 for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
The postaccident monitoring instrumentation limiting condition for operation provides the requirement of Type A and category 1 monitors that provide information required by the control room operators to:
R163 permit the operator to take preplanned manual actions to accomplish safe plant shutdown.
^ ^ " * -
Determine whether systems important to safety are performing their intended functions.
SEQUOYAH - UNIT 1 B 3/4 3-3 Amendment No. 62, 01, 149, 159,238,245
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UNITED STATLS g'
j NUCLEAR REGULATORY COMMISSION
'f WASHINGTON. D.c. 2055He
'+9 *..,*,d TENNESSEE VALLEY AUTHORITY I
DOCKET NO. 50-327
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SEQUOYAH NUCLEAR PLANT. UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE j
l
' Amendment No. 236 License No. DPR-77
- 1. _ The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 15,1999, 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 issuariGil 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 tha Commission's regulations and all applicable requirements have been satisfied.
/
j i..
- -. 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 236, 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, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9% h. Ab~-
Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 7, 1999 i
ATTACHMENT TO LICENSE AMENDMENT NO. 236 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 R'evise 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.
REMOVE INSERT Index Page V.
Index Page V 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-47 B 3/4 3-3 8 3/4 3-3
L INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION-PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ (Z) 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-10 R130 3/4 2.5 DNB PARAMETERS 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.I REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM. INSTRUMENTATION 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 3/4 3....
3/4 3-44 MOVABLE INCORE DETECTORS SEISMIC INSTRUMENTATION (DELETED) 3/4 3-45 l
3/4 3-48 METEOROLOGICAL INSTRUMENTATION 3/4 3-51 REMOTE SHUTDOWN INSTRUMENTATION CHLORINE DETECTION SYSTEMS (DELETED).
.3/4 3-55 R54 ACCIDENT MONITORING INSTRUMENTATION.
3/4 3-56 FIRE DETECTION INSTRUMENTATION (DELETED) 3,/4 3-59 lR218 DELETED
.3/4 3-68 R134
~ EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-69 SEQUOYAH - UNIT-2 V
Amendment No. 54, 130, 134, 218, 236 l
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INSTRUMENTATION' SEISMIC INSTRUMENTATION j,.
LIMITING CONDITION FOR OPERATION 3.3.3.3. This specification is' deleted.
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i (Pages 3/4 i ~45 through 3/4 3-47 are deleted) j l
I SEQUOYAH'. UNIT'2 3/4 3-45 Amendment No. 72, 203, 236 J
I
I INSTRUMENTATION r
\\
BASES 3/4,3.3.3 SEISMIC INdTRUMENTATION
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This specification is deleted.
l 3/4.3.3.4 'MF EOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that suf ficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the
'a public and is consistent with the recommendations of Regulatory Gaide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that suf-ficient capability is available to permit shutdown.and maintenance of HOT STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control room. This capability is required
.in.The event control room habitability is lost and is consistent with General BR Design Criterion 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS R54 This specification deleted.
3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring. instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accidant.
This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation R135 for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
The postaccident monitoring instrumentation limiting condition for operation provides the requirement of Type A and Category 1 monitors that R149 provide information required by the control room operators to:
Permit the operator to take preplanned manual action to accomplish safe plant shutdown SEQUOYAH - UNIT 2 B 3/4 3-3 Amendment Nos. 35, 46, 54, 72, 135, 149.228,236