ML20217B358
| ML20217B358 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/06/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217B364 | List: |
| References | |
| NUDOCS 9910120216 | |
| Download: ML20217B358 (11) | |
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UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION
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,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 j
SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 247 1
License No. DPR 77
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- 1. The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 26,1999, 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 puLlic, 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.
9910120216 991006 PDR ADOCK 05000327 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 revised through Amendment No. 247, 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, including issuance of the applicable Technical j
Requirements Manual section for use by licensee personnel.
- FOR THE NUCLEAR REGULATORY COMMISSION S.
Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 6,1999
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i ATTACHMENT TO LICENSE AMENDMENT NO, 247 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO.50-32Z Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT Index Page IX Index Page IX 3/4 7-15 3/4 7-15 3/4 7-16 B 3/4 7-4 B 3/4 7-4
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It!DEX LIMITING COllDITIONS FOR OPERATIOli AND SURVEILLAt!CE REQUIREME!!TS SECTIOli PAGE l
3/4.7.5 U LT I MAT E H EAT S I N K....................................... 3 / 4 7 - 14 R65 3/4.7.6 FLOOD PROTECTION (DELETED)................................ 3/4 7-15 l
3/4.7.7-
' CONTROL ROOM EMERGE?!CY VEllTILATION SYSTEM........
3/4 7-17 R65 3/4.7.8 AUXILIARY BUILDI!IG GAS TREATMENT SYSTEM.................. 3/ 4 7-19 3/4.7.9' SNUBBERS (DELETED)........................................
3/4 7-2) lR239 1
3/4.7.10 SEALED SOURCE ColiTAMINATION...................
3/4 7-2 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED)........................ 3/4 7-31 R231 3/4.7.12 FIRE BARRIER PENETRATIO!1S (DELETED)......................
3/4 7-41 3/4.8 ' ELECTRICAL POWER SYSTEMS
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R65 3/4.8.1 A.C.
SOURCES OPERATING.................................
3/4 8-1 j
l SHUTD0WN...................................................
3/4 8-8 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING......
3/4 8-9 3
A.C. DISTRIBUTION - SHUTDOWN.............................
3/4 8-10 D.C. DISTRIBUTION - OPERATING.............
3/4 8-11 D.C.
DI STRI BUT ION - SHUTDOW11............................. 3 / 4 8 - 14 3/4.8.3 ELECTRICAL EQUIPME!!T PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES............................................. 3/4 8-15 i
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i SEQUOYAH - UNIT 1 IX Amendment No. 61, 227, 235, 14.7 t
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l PLAIIT SYSTEMS 3/4.7.6 FLOOD PROTECTIO!!
LIMITIl!G CollDITICt!S FOR OPERATIO!!
3.7.6 This specification is deleted.
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(Pages 3/4 7-15 and 3/4 7-16 are deleted)
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SEQUOYAH - UNIT 1 3/4 7-15 Amendment No. 22, 247
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L PLANT SYSTEMS BASES l
3/4.7.5 ULTIMATE HEAT SINK (UHS)
The limitations on UHS water level and temperature ensure that suf;_elent ecoling capacity is available to either 1) provide normal cooldown of the R$3 f acility, or 2), to mitigate the ef fects of accident conditions within acceptable limits.
The limitations on the maximum temperature are based on providing a 30 R12
,.ay cooling water supply to safety related equipment wichout exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974..
The limitations on minimum water level are based on providing sufficient flow to the ERCW serviced heat loads af ter a postulated svent assuming a time-dependent drawdown of reservoir level.
Flow to the r,as sr transient heat loads (CCS and CS heat exchangers) is balance assuming a re ervoir level of R83 elevation 670.
The time-independent he loads (ESF com coolers, etc.) are balanced assuming a reservoir level of..evation 639.
lBR-10 3/4.7.6 FLOOD PROTECTION This specification is deleted.
l 3/4.7.7 CONTROL ROOM FMERGENCY VENTILATION S_YSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or
'.ts equivalent. This limitation is consistent with the requirements et General Design Criteria 19 of Appendix "A",
10 CFh 50.
ANSI H510-1975 will be used as a procedural guide for surveillance testing.
SEQUOYAH UNIT 1 S 3/4 7-4 Amendment No.
8, 79,247 l
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
- t WASHINGTON, D.C. 20555-0001 -
49 * * * * *,o TENNESSEE VALLEY AUTHORID' DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 238 License No. DPR-79 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) i dated February 26,1999, 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 Commissit ';
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the i
public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
1 he issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pubHc; and I
j E.
The issuance of this cmendment is in accordance with 10 CFR Part 51 of the i
Commission's regulat.ons and all applicable requirements have been satisfied.
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2 1
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. 238, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical i
Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance, including issuance of the applicable Technical 4
Requirements Manual sc: tion for use by licensee personnel.
FOR THE NUCLEAR REGULATORY COMMISSION b
- k. hM ^
N Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 6, 1999 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 238 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328
-. Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT index Page IX Index Page lX a
3/4 7-15 3/4 7-15 3/4 7-16 B 3/4 7-4 B 3/4 7 4 i
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4
F l
r 1
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INDEX LIMITING CONDITIO!!S FOR. OPERATION AND SURVEILLANCE REQUIREMENTS i
i SECTIOri PAGE i
3/4.7.4-ESSENTIAL RAW COOLING WATER SYSTEM...........
3/4 7-13 3/4.7.5 ULTIMATE HEAT SINK..........................
3/4 7-14 3/4.7.6 FLOOD PROTECTION PLAN (DELETED).................
........ 3/4 7-15 l
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............... 3/4 7-17 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM..............
... 3/4 7-19 3/4.7.9 SNUBBERS (DELETED)......................................... 3/4 7-21 lR225 j
3,4.7.10 SEALED SOURCE CONTAMINATION............................
. 3/4 7-41
]
3/4.7.11 FIRE SUPPRESSION SYSTEMS - (DFLETED)........................ 3/4 7-43 R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED).......................
3/4 7-52 3/4.8 ELECTRICAL POWER SISTEMS 3/4.8.1 A.C.
SOURCES Operating........................
.................. 3/4 8-1 Shutdown..................................................
3/4 8-9 l
3/4.8.2 ONSITE PUWER DISTRIBUTION SYSTEMS A.C.. Distribution - Operating............................
3/4 8-10 A.C.
Distribution - Shutdown.............................
3/4 8-11 D.C.
Distribution - Operating............................
3/4 8-12 D.C. Distribution - Shutdown.............................
3/4 8-15 f
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SEQUOYAH - UNIT 2 IX Amendment No. 218, 225, 238
N.
L' PIA!!T SYSTEMS' 3/4.7.6 -FLOOD PROTECTICfl PLA!!
LIMITIf;G CCIIDITION FOR OPERATION l'
'3.7.6 This specification is deleted, l
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(Pages 3/4 7-15 and 3/4 7-16 are deleted) j i
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SEQUOYAd - UNIT 2 3/4 7-15 Amendment Mc. 12, 238
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. PLANT SYSTEMS BASES 3/4.7.5 ULT 7 MATE HEAT SINK The limitations on the ultimate heat sink water level and temparature R70 ensure that sufficient cooling capacity is available to either 1) provide i
normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The-limitoe. ion on maximum temperature is based on providing a 30 day.
cooling water suJply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate' Heat Sink for Nuclear Plants", March 1974.
The limitations on minimum water level are based on providing sufficient flow to the ERCW serviced heat loads after a,1stulated event assuming a time dependent drawdown of reservoir level.
Flow to the major transient heat loads R70 (CCS and CS heat exchangers) is balanced assuming a reservoir level of el. 670.
The time independent heat loads (ESF room coolers, etc.) are balanced assuming a reservoir level of el. 639.
lBR-11 J/4.7.6 FLOOD PROTECTION This specification is deleted.
l 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system ?r.d 2) the control room will remain habitable fer operations perrenral during and following all credible accident conditions. The OPERABILITY cf this system in conjunction with control room design provisions is based on limiting l
the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent eith the requirements of General Design Criteria 19 of Appendix "A",
ANSI N510-1975 will be used as a procedural guide f6r surveillance testing.
1 i
SEQUOYAH - UNIT 2 B 3/4 7-4 Amendment No. 70, 238