ML20238F291
| ML20238F291 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/28/1998 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20238F294 | List: |
| References | |
| NUDOCS 9809030253 | |
| Download: ML20238F291 (19) | |
Text
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g UNIYND STATES g
j NUCLEAR REGUMTORY COMMISSION 2
WASHINGTON, L C. 30ee64001
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. TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 i
SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 235 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 February 13,1998, 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; i
i 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 i
Commission's regulations and all applicable requirements have been satisfied.
l 9809030253 980828 3
PDR ADOCK 05000327 P
PDR y
e 2-2.
Accordingly, the license is amended by changes to the Technical Speci'ications 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 F
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
235 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, in addition, paragraph 2.C.(19) of Facility Operating License No. DPR-77 is hereby amended to read as follows: *
(19) Mechanjcal Snubbers This condition is deleted 3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days afterissuance.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdo, Director Project Directorate ll-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachments: 1. Page 8 of License
- 2. Changes to the Technical Specifications Date of issuance:
August 28, 1998 l
- Page 8 of the composite license is attached to reflect this change
I,
- . e (19)
Mecchanical Snubbers This condition is deleted.
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(20)
Low Temperature Overpressure Protection (Section 5.2.2)
At the first outage of sufficent duration but no later than startup following the second refueling outage, TVA shallinstrail an overpressure mitigation system l.
which meets NRC requirements.
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(21). Control Rod Guide Thimble (Section 4.2) l 1
Prior to startup after first refueling, TVA shall submit the details of the inspection program for econtrol rod guide thimble tube wall wear for NRC approval.
(22)
TMI Action Plan Full Powest Conditions Each of the following conditions shall be completed to the satisfaction of the NRC by the times indicated:
A.
Safety Enoineerino Grouo (Section 22.2.1.B.1.2) l Prior to exceeding five percent power, TVA is required to have an onsite L
Safety Engineering Group. NRC will verify the a:dequacy of the Safety Engineering Group and its independence.
B.
Short-Term Accident Analysis and Procedure Revision (Section 22.2.l.C.11 l.
Within thirty effective full-power days, TVA shall revise Emergency Operating Procedures and brief the operators on the revision.
C.
Control Room Desian (Section 22.2.1.D.11 TVA shall consider the benefits of installing data recording and logging l
. equipment in the control room to correct the deficiencies associated with j
the trending of important parameters on strip chart recorders used in the l
control room as part of the Detailed Control Room Design Review.
l
. Implementation shall be carried out in accordance with SECY 821118.
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Amendment ff, 235 l
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 235 FACILITY OPERATING LICENSE NO. DPR-77 l
l.
DOCKET NO. 50-327 I
Revise the Appendix A Technical Specifications by removing the pages identified below and i
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 IX.
Index Page IX Index Page XIV Index Page XIV 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 3/4 7-25 B 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-6 B 3/4 7-/
B 3/4 7-7 '
NOTE: Page 6-23 is also affected by the licensee's request; however, page 6-23 was removed in it's entirety by License Amendment 233, dated July 1,1998.
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION pg g
}
3/4.7.5 ULTIMATE HEAT SINK 3/4 7-14
)
3/4.7.6
. FLOOD PROTECTION I
I/4 7-15 R65
)
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.
3/4 7-17 3/4.7.8 AUXILIARY BUILDING GAS TREA'INENT SYSTEM.
3/4 7-19 3/4.7.9 SNUBBERS (DELETED) 3/4 7-21 l
3/4.7.10 SEALED SOURCE CONTAMINATION.
3/4 7-29
.3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED) 3/4 7-31 R231 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) 3/4 7-41 3/4.8 ELECTRICAL POWER SYSTEMS R65
-3/4.8.1 A.C. SOURCES OPERATING.
3/4 8-1 SHUTDOWN 3/4 8-8 3/4.8.2 ONSITE POWER' DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING.
3/4 8-9 A.C. DISTRIBUTION - SHUTDOWN 3/4 8-10 D.C. DISTRIBUTION - OPERATING.
3/4 8-11 D.C. DISTRIBUTION - SHUTDOWN 3/4 8-14 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE
~
DEVICES 3/4 8-15 5
SEQUOYAH - UNIT 1 IX Amendment No. M, /J/7, 235
Q' 4-IEEX BASES SECTION PAGE 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK (UHS) '.
B 3/4 7-4 3/4.7.6' FLOOD PROTECTION B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.
B 3/4 7-4 3/4.7.8 AUXILIARY BUILDING GAS TREATM*:NT SYSTEM.
B 3/4 7-5 3/4.7.9 SNUBBERS (DELETED)
B 3/4 7-5 l
3/4.7.10 SEALED SOURCE CONTAMINATION.
B-3/4 7-7' 3/4.7.11-FIRE SUPPRESSION SYSTEMS- (DELETED)
B 3/4 7-7 R231 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED)
B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS-B 3/4 8-1 a
3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES B.3/4 8-2 l
3/4.9 - REFUELING OPERATIONS 1
3/4.9.1^
BORON CONCENTRATION
. B 3/4 9-1 3/4.9.2
' INSTRUMENTATION B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS
. B 3/4 9-1 3/4.9.5
' COMMUNICATIONS.
. B 3/4 9-1 3/4.9.6-
. MANIPULATOR CRANE
. B 3/4 9-2 3/4.9.7, CRANE TRAVEL - SPENT FUEL PIT AREA (DELETED)
. B 3/4 9-2 lR208 L
3/4.9.8
-RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION
. B'3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM.
.......... B 3/4 9-3 I
SEQUOYAH - UNIT 1 XIV Amendment No. /dd, III, ///, 235 i
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9 P2 ANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3 '. 7. 9. This specification is deleted.
l (Pages 3/4 7-21 through 3/4 7-25 are deleted) l l
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l SEQUOYAH --UNIT 1 3/4 7-21 Amendment No dh, d(ib, #@, 235
v' s
PLANT SYSTEMS BASES 3/4.7.8' AUXILIARY BUILDING GAS TREATMENT SYSTEM The OPERABILITY of the auxiliary building gas treatment system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are filtered prior to reaching the environment..The operation of thia ayetem and the resultant effect on offiite 86Eage calculations was assumed in the accident analyses. ANSI N510-2975 will be used as a procedural guide for surveillance testing.
Cumulative operation of the system with the heaters on for lo hours over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The minimum vacuum relief flow requirement in TS Surveillance Requirement 4.7.8.d.3 is for test purposes only.
It is intended to demonstrate an BR-6 acceptable level of ABGTS performance margin by simulating an ABSCE boundary breach.
The inability to meet the specified minimum test condition under other circumstances does not challenge the operability of the ABGTS.
2/4.7.9 SNUBBEFE This specification is deleted.
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SEQUOYAH - UNIT 1 B 3/4 7-5 Amendment No. ((,235
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e PLANT SYSTEMS BASES i
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SEQUOYAH - UNIT 1 B 3/4 7-6 Amendment No, M/, M//,235 a,
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PLANT SYSTEMS I
l BASES l
3/4.7.10 SEAT E SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct,
- source, BR-3 and special. nuclear material sources will not exceed allowable intake values.
. Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.11 FIRE SUPPRESSION SYSTEMS This Specification is deleted.
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l SEQUOYAH - UNIT 1 b 3/4 7-7 Amendment No. Id, ddd, 235 i
U o mar 6
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o'4 UNITED STATES
- j.
NUCLEAR REGULATORY COMMISSION
]
e WASHINGTON, D.C. 3088H001 4
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 225 License No. DPR-79
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 13,1998, 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 endange.ing 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.
4 s 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.
225., 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
-l Frederick J. Hebdon, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance: August 28, 1998 i
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- ATTACHMENT TO LICENSE AMENDMENT NO. 225 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 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 marginallines indicating the area of change.
REMOVE INSERT Index Page IX Index Page IX Index Page XIV Index Page XIV 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 3/4 7-25 B 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-6 B 3/4 7-7 B 3/4 7-6a NOTE: Page 6-24 is also affected by the licensee's request; however, page 6-24 was removed in it's entirety by License Amendment 223, dated July 1,1998.
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O IEIX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIQN g
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.
3/4 7.................
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 l
i 3/4.7.10 SEALED SOURCE CONTAMINATION.
3/4 7-41 l
3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED) 3/4 7-43 R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED) 3/4 7-52 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating.
3/4 8-1 Shutdown 3/4 8-9 3/4.8.2 ONSITE POWER 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 l
l SEQUOYAH - UNIT 2 IX Amendment No. fif, 225 t
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IEEK BASES SECTION Egig 3/4.7.4 ESSENTIAL RAW COOL NG WATER SYSTEM
. B 3/4 7-3 l-3/4.7.5 ULTIMATE HEAT SINK
. B 3/4 7-4 3/4.7.6 FLOOD PROTECTION
. B 3/4 7-4 3/4.7.7
-CONTROL ROOM EMERGENCY VENTILATION SYSTEM.
. B 3/4 7-4 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM.
. B 3/4,7-5 3/4.7.9 SNUBBERS (DELETED)
. B 3/4 7-5 l
l-
.3/417.10 SEALED SOURCE CONTAMINATION.
B 3/4 7-6a 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED)
..B 3/4 7-7 R218.
3/4.7.12 FIRE BARRIER PENETRATIONS. (DELETED)
........ B 3/4 7-7
'3 /4. 8 FLFCTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS.
. B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.
. B 3/4 8-2 i
3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON. CONCENTRATION.
. B 3/4 9-1 3/4.9.2
' INSTRUMENTATION.
. B 3/4 9-1
'3/4.9.3 DECAY TIME
. B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.
. B 3/4 9-1 r
3'/4. 9. 5 COMMUNICATIONS
. B 3/4 9-1
, 3 /4'. 9. 6 MANIPULATOR CRANE.
......... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA (DELETED)
. B 3/4 9-2 3/4.9.8-RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION,
. B 3/4 9-2 3/4.9.9.
~ CONTAINMENT VENTILATION SYSTEM' B 3/4 9-3
'SEQUOYAH - UNIT'2
-XIV Amendment No. h, b,225 l
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.e PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 This specification is deleted.
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1 (Pages 3/4 7-21 through 3/4 7-25 are deleted) 1 1
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SEQUOYAH - UNIT 2 3/4 7-21 Amendment Nos. M, Md,225
y.
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PLANT SYSTEMS BASES l.
3/4.7.8 ' AUXILIARY BUILDING CAS TREATMENT SYSTEM The OPERABILITY of the auxiliary building gas treatment system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage' calculations was assumed in the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The minimum vacuum relief flow requirement in TS Surveillance Requirement 4.7.8.d.3 is for test purposes only.
It is intended to demonstrate an BR-8.
acceptable level of ABGTS performance margin by simulating an ABSCE boundary breach. 'The' inability to meet the specified minimum test condition under other circumstances does not challenge the operability of the ABGTS.
3/4.7.9 SNUBBERS This specification is deleted.
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l SEQUOYAH - UNIT 2 B 3/4 7-5 Amendment 4, 225 l
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a PLANT SYSTEMS BASES This page is deleted SEQUOYAH - UNIT 2 B 3/4 7-6 Amendment Nos. f, Y/3, 225
O 2
9 EASES I
i 3/4,7.10 SEATrn SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak
(
testing, including alpha emitters, based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, i
and special nuclear material sources will not exceed allowable intake values.
j Scaled. sources are classified into three groups according to their use, with surveillance requirements commensurate'with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
SEQUOYAH - UNIT 2 B 3/4 7-6a Amendment Nos, jf, ///, 225