ML20210J584
| ML20210J584 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/12/1997 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210J590 | List: |
| References | |
| NUDOCS 9708180153 | |
| Download: ML20210J584 (38) | |
Text
______ __ _ _ _ - _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ - -
km atroq p
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 30666 4 001 s,...../
I lt'NNESSEE VALLEY AUTHORITY l
DOCKET NO. 50-327 l
SE0VOYAH NUCLEAR PLANT. UNIT 1 j
AMENDMENT TO FACILITY OPERATING LICENSE i
l l
Amendment No. 227 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 Seatember 26. 1996, as supplemented on August 12.
1997, complies wit 1 the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic 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 (1) 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.
9708180153 970812 PDR ADOCK 05000327 P
PDR 7
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in A)pendices A and B. as revised through Amendment No. 227. are heresy incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
Also, the license is amended by replacing Paragraph 2.C(16) on page 6 of l
Facility Operating License DPR-77 with the following:
(16) Fire Protection TVA shall implement and maintain in effect all provisions of l
the approved fire protection program referenced in Sequoyah Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG-0011.
Supplements 1. 2. and 5. NUREG-1232. Volume 2. WRC letters dated May 29 and October 6. 1986. and the Safety Evaluation issued on August 12. 1997, for License Amendment No. 227 subject to the following provision:
TVA may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
3.
This license amendment is effective as of its date of issuance to be implemented no later than 45 days after its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4.
Frederick J. Hebton. Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Changes to the Technical Specifications
- 2. -Page 6 of license
- Date of Issuance: August 12, 1997
h'.
t ATTACHMENT TO' LICENSE AMENDMENT-NO. 227 FACILITY OPERATING LICENSE NO: DPR-77 DOCKET NO. 50-327 Rev'ise-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 ofJchange.
REMOVE INSERT V
V IX IX
-XIV XIV 3/4 3-58 3/4 3-58 3/4 3-59 through 3/4 3 3/4 3-59 3/4~7-31 3/4 7 3/4 7-32 3/4 7 3/4 7-33 3/4 7-34
- 3/4 7-35 3/4 7-35 3/4-7-36 3/4 7-37 3/4 7-37 3/4 7-38 through 3/4 7-40 3/4 7-38 3/4 7-41 3/4 7-41 B 3/4 3-4 B 3/4 3-4 B 3/4 7-7 B 3/4 7-7 B 3/4 7-8 B 3/4 7-8
- 6-2 6-2 m..
4
9 1895%
LIMITING CONDITIONS.FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION F,82E 3/4.2 POWER DISTRIB1TTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4 2-1 l
3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ (Z) 3/4 2-5 l
3/4.2.3 NUCLEAR ENTEALPY HOT CHANNEL FACTOR,
3/4 2-10 R142 l
3/4.2.4 QUADRANT POWER TILT RATIO.
3/4 2-12 3/4.2.5 DNB PARAMETERS 3/4 2-15 3/4.3 INSTRLMENTATION i
l _-
3/4.3.1 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 3-39 MOVABLE INCORE DETECTORS 3/4 3-43 SEISMIC INSTRUMENTATION.
3/4 3-44 METEOROLOGICAL INSTRUMENTATION 3/4 3-4*/
REMOTE SHUTDOWN INSTRUMENTATION 3/4 3-50 CHLORINE DETECTION SYSTEMS (DELETED) 3/4 3-54 ACCIDENT MONITORING INSTRUMENTATION.
3/4 3-55 FIRE DETECTION INSTRLHENTATION (DELETED) 3/4 3-58 l
DELETED.
3/4 3-70 R152 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-71 SEQUOYAH - UNIT 1 V
Amendment No. 62, 138, 148,227
INDER LIMITING CONDITIONS FOR OPERATION AND SURVEILLAN,CE REQUIREMENTS SECTION P2fal
_3/4.7.5 ULTIMATE HEAT SINK
~.
3/4 7-14 3/4.7.6 FLOOD PROTECTION 3/4'7 R65 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.
3/4 7-17 1
3/4.7.8 AUXILIARY BUILDING GAS TREA7NENT SYSTEM.
3/4 7-19 l
l 3/4.7.9 SNUBBERS-l 3/4 7 I 3/4.7.10 SEALED SOURCE CONTAMINATION.
3/4 7-29 3/4.7.11-FIRE SUPPRESSION SYSTEMS (DELETED) 3/4 7-31 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED).
3/4 7-41 3/4.s ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES R65 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.........
A.C. DISTRIBUTION - SHUTDOWN 3/4 8-10 D.C. DISTRIBUTION - OPERATING,
3/4 8-11 D.C. DISTRIBUTION.- SHUTDOWN 3/4 6-14 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES i
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.
3/4 6-15 i
SEQUOYAH - UNIT 1 IX Amendment No. 61,227
T-l MEEK BASES SECTION PAgg 3/4.7.4
. ESSENTIAL RAW COOLING WATER SYSTEM-
.-. B 3/4 7-3
- 3/4.7.5:
ULTIMATE NEAT. SINK-(UNS)
~. B 3/4 7-4 3/4.7.6 FLOOD PROTECTION 1
. B 3/4 7-4
-1 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM,
. B 3/4 7-4 3/4.7.9
_. AUXILIARY BUILDING GAS TREA'INENT SYSTEM.
.. B=3/4 7-5 j ;-
3 /4. 7. 9 :-
SNUBBERS-
............................ -. B 3/4 7-5 i-I 3/4.7.'10 SEALED-SOURCE CONTAMINATION.
. B 3/4 7-7, I
r.
3/4.7.11 FIRE SUPPRESSION SYSTEMS'(DELETED)
.. B 3/4-7-7.
l' 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 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...
. B 3/4 8-2 3 /4. 9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION
. ~B 3/4 9-1
- 3/4.9.2 INSTRUMENTATJON
. B 3/4 9-1 3/4.9.3-DECAY TIME.
................-....... B 3/4 9-1 3/4.9.4-C'ONTAINMENT 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 -lR208-3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION
. B 3/4 9-2
. 3/4.9.9 CONTAINMENT VENTILATION SYSTEM.
. B 3/4 9-3 i
SEQUOYAN - UNIT 1 XIV Amendment No. 157, 204,227
INSTR 2.1MENIATION IIEE_pETECTION INSTRIDENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 This Specification is deleted, i
i i
e SEQUOYAH - UNIT 1 3/4 3 58 Amendment No. 36 227 t
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PIANT SYSTEMS 3 /4.' 7. i1 ~ FIRE SUPPRESSION SYSTEME FIRE SUPPRESSION WATER SYSTEM
- LIMITING-CONDITION FOR OPERATION--
.3.7.11.1-This specification is' deleted..
Pages 3/4 7-31 and 3/4 7-32 are deleted.
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'SEQUOYAH - UNIT 1 3/4 7-31 Amendment No. 13, 36; 66, 186, 227 s
PLANT SYSTEMS i
SPRAY AND/OR EPRINKtrR SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 This specification is-deleted.
l r,
Pages 3/4.7-33 and 3/4 7-34 are deleted.
SEQUOYAH --UNIT 1 3/4 7-33 Amendment No. 12, 36,227
't
.d
PLANT SYSTEMS
& SYSTEMS LIMITING CONDITION FOR OPERATION-i 3.7.11.3-This Specification is deleted l
l
- i Peges 3/4-7-35 and 3/4 7-36 are deleted.
1 i
1 SEQUOYAH. UNIT 1 3/4 7 35 Amendment No. 12, 36, 96,227
.. ~ -.. _. ~....
4.
PLANT SYSTEMS FIRE HOSE STATIONS 3
LIMITING CONDITION FOR OPERATION a-3.7.11.4 This-Specification is deleted.
i, 4
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1 1
4
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i SE(rUOYAH - UNIT 1 3/4 7-37 Amendment No. 36, 114, 143,227 I
s' PLANT SYSTEMS i
TABLE 3.7 5 FIRE HOSE STATIONS-I l
I' l
[..
l l
This Table is deleted (Pages 3/4 7-38 through 3/4 7-40 are deleted) i SEQUOYAH - UNIT 1 3/4 7-38 Amendment No. 13.227
.c
-PLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION-3.7.12 This specification is deleted, i
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SEQUOYAH - UNIT 1 3/4 7-41 Amendment No. 36,22'/
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INSTRTJMENTATION BASES' 4
3/4.3.3.'8 FIRE DETECTION INSTRUMENTATION
.This specification is deleted.
3/4.3.3.9 i-
-This specification is deleted.
3/4.3.3.'10 EXPLOSIVE GAS MONITORING INSTRtMENTATION This instrumentation' includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPER-ABILITY and use of this instrumentation is consistent with the requirements for monitoring potentially explosive gas mixtures.
4 4-I 4
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's SEQUOYAH - UNIT 1 B 3/4 3-4 Amendment No. 43, 148, 149,227 l R153 s
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3-P2 ANT SYSTEMS BASES SNUBBERS (Continued) location, etc.),.and the' recommendations of Regulatory Guide 8.8 and 8.10.
The R43 addition or deletion of any hydraulic.or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
3/4.7.10 SEAtrn SOURCE C0h7 AMINATION 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 pf 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 machanism (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.
I 3/4.7.11 FIRE SUPPRESSION SYSTEMS l
l-This Specification is deleted.
1 SEQUOYAH - UNIT 1-B-3/4 7-7 Amendment No. 39, 22"/
e
P2 ANT SYSTEMS BASES 3/4.7.12 ' FIRE BARRIER PENETRATIONE
' This' Specification'is deleted.
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SEQUOYAH - UNIT 1 3 3/4 7 8 Amendment No. 39, 227 '
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ADMINISTRATIVE CONTROLS w
A nadiological Control technicianshall be onsste when fuel is in c.
the reactor, RC2 d.
All CORE ALTERATI9NS shall be observed and directly supervised by either a licenset Senior Reactor Operator or Senior Reactor Operator FP l
Limited to Puel Handling who has no other concurrent responsibilities during this operation.
e.
Delettd l
The Operations Superintendent shall hold a Senior Reactor Operator l
f.
- license, R160 l
Administrative procedures shall be developed and implemented to limit f
g.
the working hours of unit staf f who pe.' form safety-related functions l
(i.e., senior reactor operators, reactor operators, assistant unit operators, Radiological Contrc1, and.1y maintenance personnel),
l Adequate shif t coverage shall be maintained without routine heavy use f
of overtime.
l The objective shall be to have operating personnel work a normal e-hour day, 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the unit is operating, i
However, in the event that unforseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed 1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An individual should not be permitted to work more ths-aours in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 s ur period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time.
R156
'A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between votk 3.
periods, including shift turnover time.
4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized in advance by the Plant Manager or his designee, in accordance with approved administrative procedures, or by higher lovels of management, in accordance with established R182 procedures and with documentation of the basis for granting the deviat$on.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designet to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines *is not authorired.
- The Radiological control technician may be offsite for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required peo,*. ions.
SEQUOYAH - UNIT 1 6-2 Amendment No. 32, 56, 74, 152, 156, 17s, 227 4
6-j.
(c)
By no later than June 30,1982, all safety related electrical equipment in the facility shall be qualined in accordance with the provisions of:
Division of Operating Reactors
- Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in l
Operating Reactos" (DOR Guidelines); or, NUREG 0588, " Interim l
Staff Position on Environmental Qualification of Safety Related Electrical Equipment," December 1979. Copies of these documents are attached to the Order for Modificatior -f Licence DPR 77 dated November 6,1980.
(13)
Imss of Non Class IE Instmmentation and Control Room System Bus Durine Operation (Section 7.10)
Prior to exceeding five percent power, TVA must complete revisions to plant i
emergency procedures to the satisfaction of the NRC.
(14)
Encineerine Safety Feature (ESP) Reset Controls (Section 7.11)
I in confonnance with IE Bulletin 80-06, TVA shall test the system to identify j
any further areas of concern, and TVA shall review the control schemes to determine tha: they are the best in terms of equipment control and plant safety.
The results of these test and review efforts shall be provided to the NRC in accordance with the bulletin.
(15)
Diesel Generator Reliability (Section 8.3.1)
Prior to operation following the first refueling. TVA shall implement the following design and procedure modifications as outlined in Section 8.3.1 of SER Supplement No. 2. These include: (a) Moisture in Air Starting Systemt (b) Turbocharger Gear Drive Problem; and (c) Personnel Training.
(16)
Fire Protection TVA shall implement and maintain in effect all provisions of the approved fire protection program referenced in Sequoyah Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG 00ll, Supplements 1,2, and 5 NUREG-1232 Volume 2, NRC letters dated May 29 and October 6,1986, and the Safety Evaluation issued on August 12, 1997, for License Amendment No. 227, subject to the following provision:
TVA may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 9, 227
?
p UNITED STATES NUCLEAR REGULATORY COMMISSION wAsMiwatow, o.c. steeewooi g,....t TENNESSEE VALLEY AUTHORITY DOCKET NO. 50 328 SE000YAH NUCLEAR PLANT. UNIT 2
@.LUDMENTTOFACILITYOPERATINGLICENSE Amendment No. 218 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 Seatember 26, 1996, as supplemented on August 12, 1997, complies wit 1 the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, 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 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 Comission's regulations and all applicable requirements have been satisfied.
f
.a 2.
Ac'.F dit' gly, the license is amended by changes to the Technical Sptifications as indicated in the attachment to this license amendment.
- Pat Araph 2.C.(2) of Facility Operating License No. DPR-79 is hereby
-amended to read as-follows:
o (2) Technical Soecifications I
l The Technical Specifications contained in A>pendices A and B. as revised through Amendment No. 218, are hereay-incorporated in the license.
The licensee shall o the-Technical Specifications. perate the facility in accordance with J
Also, the license is amended by replacing Paragraph 2.C(13) on page 6 of Facility Operating License DPR 79 with the following:
(13) Fire Protection 1VA shall implement and maintain in effect all provisions of 1
the approved fire protection program referenced in Sequoyah i
Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG-0011.
Supplements 1, 2 and 5. NUREG 1232. Volume 2. NRC letters dated May-29 and October 6. 1986, and the Safety Evaluation issued on August-12.-1997 for License Amendment No. 218.
subject to the following provision:
TVA may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
l 3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after its issuance.
FOR THE NUCLEAR REGULATORY-COMMISSION 1
1 s
- r Frederick J, Hebd6n Director 1
Project Directorate 11 Division of Reactor Projects - 1/l!-
i Office of Nuclear Reactor Regulation
Attachment:
- 1. Changes to the Technical Specifications
- 2. Page 6 of license
- Date of Issuance:
August 12, 1997 l
r
7 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 218 FACILITY OPERATING LICENSE NO. OPR-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 b the captioned amendment number and contain marginal lines indicating t e area of change.
EWQy1 INSERT y
v l
IX IX l
xlv xlv 3/4 3 59 3/4 3 59 3/4 3 60 through 3/4 3 67a 3/4.3 60 3/4 7-43 3/4 7-43
-3/4 7 44 3/4 7-45 3/4 7-45
{
3/4 7 46 3/4 7-47 3/4 7-47 3/4 7-48 3/4 7-48 3/4 7 49 through 3/4 7 51 3/4 7-49 3/4 7-52 3/4 7-52 B 3/4 3 4 B 3/4 3 4 B 3/4 7-7 B 3/4 7-7 8 3/4 7 8 B 3/4 7 8 6-2 6-2
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS IE.CIlDE l
T.26t1 3/4.2 POWER DISTRIBUTION LIMP",1 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANIEL FACTOR PQ(Z)
. 3/4 24 3/4.2.3 NUCLEAR ENTHALPY HOT CHANIEL 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 1
)
3/4.3.1 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 3-40 MOVABLE INCORE DETECTORS 3/4 3-44 SEISMIC INSTRUMENTATION.
3/4 3-45 METEOROLOGICAL INSTRUMENTATION 3/4 3-48 REMOTE SHUTDOWN INSTRUMENTATION 3/4 3-51 CHLORINE DETECTION SYSTEMS (DELETED).
.3/4 3-55 R54 ACCIDENT MONITORING INSTRUMENTATION.
3/4 3 56 FIRE DETECTION INSTRUMENTATION (DELETED) 3/4 3-59 l
, DELETED.
.3/4 3-68 R134 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-69 s
I
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'SEQUOYAH - UNIT 2 V
Amendment No. 54, 130, 134.218 f
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INDEX
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LIMITING CONDITIONS FOR CPERATION AND SURVEILLANCE REQUIREMENTS SECTIeN ELgz 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 15 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 l
3/4.7.9 SNUBBERS 3/4 7-21 3/4.7.10 SEALED SOURCE CONTAMINATION.
3/4 7-41 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED) 3/4 7-43 l
3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED)
-3/4 7-52 3/4.9 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating.
3/4 81 Shutdown
. 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating.
3/4 6-10 A.C. Distribution - Shutdown 3 /4 B-11 D.C. Distribution - Operating.
3/4 8-12 D.C. Distribution - Shutdown-3/4 8-15 SEQUOYAM - UNIT 2 IX Amendment No.218
i 1.UWIZ RASES i
P SrCTION g;,g l
3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM B 3/4 7 3 3/4.7.5 ULTIMATE HDT 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 l
3/4.7.8 AUXILIARY BUILDING GAS TREA*IMENT SYSTEM.
B 3/4 7-5 3/4.7.9 SNUBBERS B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION.
B 3/4 7-6a I
l 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED)
B 3/4-7-7 l
3/4.7.12 FIRE BARRIER PENETRATIONS (DF.LETED)
B 3/4 7-7 t
I 3 /4. 8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION j
SYSTEMS
..... B 3/4 6-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.
B 3/4 6-2 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.
B 3/4 9-1 3/4.9.2 INSTRUMENTATION.
B 3/4 S-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 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 - SP."NT FUEL PIT AREA (DELETED)
B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.
B 3/4 92 3/4.9.9 CONTAINMENT VENTILATION SYSTEM B 3/4 9-3 l
l SEQUOYAH - UNIT 2 XIV Amendment No. 194, 218 e4
Fftr DETECTION IWBTa m 1 TION LIMITING CONDITION FOR OPERATIrm 3.3.3.9 Thin SpecAficatien is deleted.
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4 SEQUoYAN - UNIT 2 3/4 3 59 Amendment No. 28,218 '
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PLANT SYETINS 3/4.7,11 ' FIRE RUpparmaION SYETEME
= Fiat suppareBION WATER BYSTEM j;
LIMITING CONDITION FOR OPERATION-3.7.11.1 This specification is deleted.
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Pages 3/4 7-43 and 3/4 7-44 are deleted.
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SEQUOYAH -. UNIT 2 3/4 7-43 Amendment No.'4, 28, 58, 178,218 I
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PLAIM SYSTEMS SPRAY AND/OR SPRIfW1ER SYSTEMS LIMITING CONDITION FOR OPERATION
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3.7.11.2 This specification is deleted.
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Pages 3/4 7-45 and 3/4 7 46 are deleted.
I SEQUOYAH - UNIT 2 3/4 7-45 Amendment No. 28, 178.218 r
P2Jd1T SYSTEMS CO, SYSTEMS LIMITING CONDITION FOR OPERATION l
3.7.11.3 This specification is deleted.
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I SEQUOYAH - UNIT 2 3/4 7-47 Amendment No. 28, 85 218 I
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PLANT SYSTEMS I
FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION l
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3.7.11.4 This Specification is deleted.
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e SEQUOYAH - UNIT 2 3/4 7-48 Amendment No. 32 218 r
l-l TABLE 1.7 1 FIRI HOEI STATIONE
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This Table is deleted (Pages 3/4-7-49 through 3/4 7-51);
i SEQUOYAM - UNIT 2 3/4 7 49 Amendment No. 104, 124,218 4
PLhMT SYSTEMS 3/d.7.12 FIRE minRIra prierT3A7tpg LIMITING CONDITION FOR OPERATION 3*7+12-Thi8 Specification is deleted, I
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l stocoYAx - UNIT 2 3/4 7 5t Amendment No. 28,218
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INSTRtHENTATION
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BASES 3/4.3.3.9 FTRE DETECTION INSTRtHENTATION This specification is deleted.
3 /4. 3. 3. 9 This Specification is deleted.
3/4.3.3.IO EXPLOSIVE GAS lONITORING INSTRtMENTATION R134 This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERA.
BILITY and use of this instrumentation is consistent with the requirements for monitoring potentially explosive gas mixtures, i
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l SEQUOYAH - UNIT 2 B 3/4 3-4 Amendment Nos. 35, 46, 134, 218
3r PLMfT.1YSTEMS BASES 3/4.7.11 FIRE SUPPREERION sy3 TEM 3 This specification is deleted.
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I SEQUOYAH - UNIT 2-B 3/4 7-7 Amendment No4216 f
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SEQUOYAH -. UNIT 2 3 3/4 7 8 Amendment No. 218 t
ADMINISTRATIVE CONTR8LS A Radiological control technician" shall be onsite when fuel is in c.
R50 the reactor.
d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor operator Limited to Puel Handling who has no other concurrent responsibilities during this operation.
e.
DELETED I
f.
The operations Superintendent shall hold a senior Reactor Operator lR145 license.
g.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (i.e., senior reactor operators, reactor operators, assistant unit operators, Radiological Control, and key maintenance personnel).
l Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating R142 personnel work a normal 8-hour day, 40-hour week while the unit is operating.
However, in the event that unforseen problems require l
substantial amounts of overtime to be used, or during extended l
periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:
1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shif t turnover time.
3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shif t turnover time.
4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized in advance by the plant Manager or his designee, in accordance with approved administrative R169 procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designet to assure that R142 excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
8The Radiological Control technician may be offsite for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
SEQUOYAH - UNIT 2 6-2 Amendment Nos. 50 66, 142, 145, 169, 218
. 4 (13)
Fire ProtectioD TVA shall implement and maintain in effect all provisions of the acproved fire protection program referenced in Sequoyah Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG-0011, Supplements 1,2, and 5 NUREG 1232, Volume 2, NRC letters dated May 29 and October 6,1986, and the Safety Evaluation issued on August 12, 1997, for License Amendment No. 218, subject to the following provision:
l TVA may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire, l
(14) f,bmnliance With Reculatorv Guide 1.97 TVA shall implement modifications necessary to comply with Revision 2 of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"
dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage.
(15)
Corrosion of Carbon Steel Piping TVA shall carry out a surveillance program on corrosion of carbon steel piping in accordance with TVA document SQRD 50-328/81-10 dated August 25,1981, and procedures for implementation are to be submitted for NRC concurrence by October 15, 1981.
(16)
NUREG-0737 Conditions (Section 22.2)
Each of the following conditions shall also be performed to the satisfaction of the NRC:
Shift Technical Advisor (Section 22.2. I. A.1 1) a.
TVA shall provide a fully-trained on-shift technical advisor to the stdft supervisor, b.
Independent Safety Encineerine Group (Section 22.2.1.B.1.2)
TVA shall have an onsite Independent Safety Engineering Group.
l Amendment No. 45,218
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