ML20012E835
| ML20012E835 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/22/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012E836 | List: |
| References | |
| NUDOCS 9004060404 | |
| Download: ML20012E835 (14) | |
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UNITsD sTATss j
NUCLE AR CECUL ATCRY COMMISSION i
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TENNESSEE VALLEY AUTHORITY
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DOCKET N0. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 i
AMENDNENT TO FACILITY OPERATING LICENSE l
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i Amendment No. 133 License No. DPR-77 l
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The Nuclear Regulatory Commission (the Comission) has found that:
c A.
The application for amendment by Tennessee Valley Authority (the
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licensee) dated October 5,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
I and the Commission's rules and regulations set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules anc regulations of the Commission; t
C.
There is reasonable assurance (4) that the activities suthorized by l
this amendment can be conducted without endanger':ag the be61tt Gnd iafety of the public, and (ii) that such activities will bet cenducted in compliance with the Commission's regulations;
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D.
The issuance of this amendment will not be inimicti to the cunmcn I
defense ?,od seenrity or to the hecith and safety of th.e public; and f.
The issuance of this amendment is in accordar.cc with 10 CFR Pa-t 51 of the Commission's regulations and all applicable requirenents hsve been satisfied.
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2.
Accordingly, the license is amended by chenpes to the Technical I
Specifications as indicated in the attachment to this license amendment r
and paragraph 2.C.(2) of facility Operating License No. DPR 77 is hereby j
amended to read as follows:
j (2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 131 are hereby incorporated in the j
license. The licensee shall operate the facility in accordance with j
the Technical Specifications.
6 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMM!$$10N 1
hD es Suzanne ack, Assistant Director i
for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 22, 1990
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1 ATTACHM(NT TO LICENSE AMENDMENT N0.133 FACILITY OPERATING LICENSE NO. DPR 77 j
l DOCKET NO. 50-327
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Revise the Appendix A Technical $pecifications by removing the pages identified i
below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
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REMOVE INSERT Y!
VI 3/4 4-28 3/4 4-28 l
B 3/4 4 2 B 3/4 4-2 l
B 3/4 4-14 B 3/4 4 14 l
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e INDEX LIMITING CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l
SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM r
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation...............................
3/4 4 1 Hot Standby...............................................
3/4 4-la Shutdown..................................................
3/4 4 2 3/4.4.2 SAFETY VALVES - SHUT 00WN..................................
3/4 4-3 L
3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING Safety Valves - Operating.................................
3/4 4-4 Relief Valves - Operating.................................
3/4 4-4a i
3/4.4.4 PRESSURIZER...............................................
3/4 4-5 i
3/4.4.5 STEAM GENERATORS..........................................
3/4 4-6 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detect',on Systtms..............................
3/4 4-13 Operational L$tlage...........
3/4 4-14 i
3/1.4.7 CHEMISTRY.............................,,
3/4 4-16 3./4. 4. 6
$PECIFIC ACTIVITY.................
3r4 4-19 i
3/4.4.5 PRES $r;RE/ TEMPERATURE LIMITS 7eacter Cooiant System.........
5/4 4 23 j
Pressurher.....................
3/4 4 26 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Cetponents.....................
3/4 4-27 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS.........................
3/4 4-28 l
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1 SEQUOYAH - UNIT 1 VI Amendment No. 116. 133
g REACTOR COOLANT $Y$ TEM 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS
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LIMITING CONDITION FOR OPERATION 3.4.11 At least one Reactor Coolant System Head Vent (RCSHV) path shall be i
OPERABLE.*
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With no RCSHV path OPERABLE *, restore at least one path to OPERABLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS b 4.4.11 Each RCSHV path shall be demonstrated OPERABLE at least once per 18 l
months by:
i a.# Verifying that the upstream manual isolation valves are locked in the open position.
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Operating each remotely controlled valve through at least one cycle from the control room, and c.
Verifying flow through each RC$HV path, f
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- Irioperable paths must be maintained closed with power removed from the valve actuators.
If any RCSHV path is declared inoperable while in an applicable MODE, power shall be removed from the valve actuators within one hour.
- The requirement to verify that the upstream manual isolation valves are locked in the open position is waived until the Cycle 4 refueling outage.
This waiver is granted on a one-time basis.
At the first Mode 5 outage following issuance of the above waiver, a flow verification test will be performed to verify that the manual isolation valves are open.
l SEQUOYAH - UNIT 1 3/4 4-28 Amendment No. 116, 123, 133 i
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BA$ts safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overprsssurization.
I During operaf en, all pressurizer code safety valves must be OPERABLE to t
prevent the RC3 t N.n being pressurized above its safety limit of 2735 psig.
The combined relief capacity of all of these valves is greater than the maximum surge rato resulting from a complete loss of load assuming no reactor trip 1
until the first Reactor Protective System trip set point is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves, j
Demonstration of the safety valves' lift settings will occur only during
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shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
The power operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design tra.nsients up to and including the design step load decrease with steam dump.
Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.
Each PORV has a remotely operated block valve to provide positive shutoff capability should a relief valve become inoperable.
The PORVs also function to remove non-condentibits cr steam from the pressuciter.
i 3/4.4.4 PRESSURIZER The lic.it on the maninum water volume in the presturizar assures t%t the carameter b maint.ained within tne nor.a1 steady state envelope of operatiol assumed in tt+ S/,R.
The li!rit i6 :ansistent with the initial SAR anumptiens.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period'c surveillan;e is tufficient to ensure thst tne parameter is rest 9 red to within its limit following enweted transient operation.
The pwimut rater veh.m alJo emuret that a steam bubble is formed and thus the r
E! it not a hydrsulically tolid s); tem The re ;vit enent that 150 kw of pressurir e neater, and tr.eir sv,x it'ed controls be cep4ble of being tupplied electrical power from an emergency bus provides assurance that the plant w d )
be able to control reactor coolant pressure and establish natural circulation
- enditions.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
SEQUOYAH - UNIT 1 B 3/4 4-2 Amendment No.12,133
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SASES 3/4.4.10 $TRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness l
of these components will be maintained at an acceptable level throughout the life of the plant.
These programs are in accordance with Section XI of the i
ASME Boiler and Pressure Vessel Code and applicable Addenda as required by i
10 CFR Part 50.55a(g) except where specific written relief has been granted by j
the Commission pursuant to 10 CFR Part 50.55a (g)(6)(i).
Components of the reactor coolant system were designed prior to issuance of Section XI of the ASME Boiler and Pressure Vessel Code.
These components will be tested to the extent practical within the limitations of the original plant design, geonetry, and materials of construction of the components, i
3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS I
i The function of the RCS head vents is to remove non-condensables or steam from the reactor vessel head.
This system is designed to mitigate a possible l
condition of inadequate core cooling, inadequate natural circulation, or in-ability to depressurite the RHR System initiated conditions resulting from the accumulation of non-condensable gases in the Reactor Coolant System.
The
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reactor vessel head vent is designed with redundant safety grade vent paths, i
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l SEQUOYAH - UNIT 1 8 3/4 4-14 Amendment No. 116, 133
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NUCLE AR CEGUL ATORY COMMISSION w A&Hiev070N, D. C. 20666
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I TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-320 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessae Valley Authority (the Itcensee)datedOctober5,1989,complieswiththestandardsand t
requirnents of the Atomic Energy Act of 1954, as (msnded (trie Act),
t and the Commission's. rules and regul# tier,s set forth in 10 CER l
e Chapter I; r
D.
The facility wi'l operate in t nfomity ylth the appl (*stion. ?be provisions Jf the Act, and the ruler.*.nc. ret 11ations of the e
Comission; f
C.
There is reesonsole assurance (1) that the activities authorized by this Amtndnent. ca1 be conducted wi thout endar.gerir,tj the hea'ssh and l
safecy of the public, and (11) that such activitics will be conducted in ompliance with the Comission's regulationse l
D.
The issuance of this anendment will not bo 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 of the Comission's regulations and all applicable requirements have been satisfied.
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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. OPR-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. 120, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with l
the Technical Specifications.
t 3.
This license amendment is effective as of its date of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION hcA 4
.2 w4 Suzanne lack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Reguistion
Attachment:
Changet to the Technied)
SMcifications hie of Issuance: March 22. 1990 I
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4 ATTACHMENT TO LICENSE AMENDMENT NO.120 i
FACILITY OPERATING LICENSE NO. DPR 79 DOCKET NO. 50 328 l
Revise the Appendix A Technical Specifications by removing the pages identified l
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, j
REMOVE INSERT l
i VI V!
3/4 4-34 3/4 4 34 l
B 3/4 4 2 B 3/4 4 2 B 3/4 4 15 8 3/4 4-15 i
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l l#PU LIMITING CONDITIONS FOR OPERATION AND $URVE!LLANCE REQUIREMENTS I
$ECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION I
Startup and Power Operation...............................
3/4 4 1 Hot $tandby...............................................
3/4 4 2 Hot Shutdown.............................................,
3/4 4 3 Cold Shutdown.............................................
3/4 4 5 3/4.4.2
$AFETY VALVES
$HUTD0WN.....,,,.........................
3/4 4 6 3/4.4,3
$AFETY AND RELIEF VALVE $
OPERATING Safety Valves Operating...................................
3/4 4 7 Relief Valves 0perating..................................
3/A 4 8 3/4.4.4 PRES $URIZER............................................<,.
3/4 4 9 3/4.4.5 STEAM GENERATORS..........................................
3/4 4 10 3/4.4.6 REACTOR 000LANT $YSTEM LEAKAGE i.eaktge Detecticn Systems.....
3/4 A 17 Operational Leckage..................................
?/4 Flo 3/4,4.?
CHEMISTRY.................................................
3/4 4 21 e
3/4.4.4 SPECIFIC ACTIVITY.........
3/4 4-24 L
3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System....................................
3/4 4-28 Pressurizer...............................................
3/4 4 32 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components.....................
3/4 4 33 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS........................
3/4 4 34 i
SEQUOYAH - UNIT 2 VI Amendment No. 106. 120 l
l REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR COOLANT SYSTEM HEAD V(NTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one Reactor Coolant System Head Vent (RC$HV) path shall be OPERABLE.*
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With no RCSHV path OPERABLE *, restor.e at least one path to OPERABLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUIDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
The provisions of $pecification 3.0.4 are not applicable.
$URVEILLANCE REQUIREMENTS 4.4.11 Each PiSHV path shall bt demonstrated OptRABLE st least once per l
15 mentbr by:
Verifying thkt the epstraam niaaual bolstion valves are locked in
.a.#
r the oper, position, l
h-Opert',iro ecch 'enietely controllod valve through 4t letM olie cycle fror ',l.c *ontrol room. and d
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Verifying flow through each RC$HV path.
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- Inoperable paths must be maintained closed with power removed from the salve actuators.
If any RCSHV path is declared inoperable while in an applicable MODE, power shall be removed from the valve actuators within one hour.
- The requirement to verify that the upstream manual isolation valves are locked in the open position is waived until the Cycle 4 refueling outage.
This waiver is granted on a one-time oasis.
At the first Mode $ outage following issuance of the above waiver, a flow verification test will be performed to verify that the manual isolation valves are open.
$EQUOYAH - UNIT 2 3/4 4-34 Amendment No. 106, 112, 120
REACTOR COOLANT $Y$ TEM SA$[$
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3/4.4.2 and 3/4.4.3 SAFETY AND RELIEF VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2725 psig.
Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at the valve set point.
l The relief capacity of a single safety valve is adequate to relieve any over-4 pressure condition which could occur during shutdown.
In the event that no sa#ety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.
During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.
The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip r
until the first Reactor Protective System trip set point is reached (i.e., no credit is tcken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.
Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
The power operated reliet valves (PORVr) s.9J *tasm but+1e function to I
tv)ieve RCS pressure during til design trartientf up to art. Incicding the ce),49n rtop load decruso with itetm dump.
@traticn of the PORVs minimizes the unde.sirable openir.C of the coring *ioadtd prnsurizer code safety valves.
Each PORV has a remotely operateo block valve to provide positive shutoff capability should a rel M valve becore i.Uperable.
The PORVs also function to :emove non-condersibles or tteam from the pressurizer.
3/4.4.4 PRES $URIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady state envelope of operation assumed in the SAR.
The limit is consistent with the initial SAR assumpt' ions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation.
The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system.
The requirement that 150 kw of pressurizer heaters and their associated ccatrols be capable of being supplied electrical power from an emergency bus provides assurance that the plant will be able to control reactor coolant pressure and establish natural circulation conditions.
SEQUOYAH - UNIT 2 B 3/4 4-2 Amendment No.120 l
REACTOR C00LANT SYSTEM SA$i$
3/4.4.11 ~ REACTOR COOLANT SYSTEM HEAD VENTS The function of the RCS head vents is to remove non condensables or steam from the reactor vessel head.
This s condition of inadequate core cooling,ystem is designed to mitigate a possibleinad to depressurite the RHR System initiated conditions resulting from the accumulation of non condensible gases in the Reactor Coolant System.
The reactor vessel head vent is designed with redundant safety grade vent paths.
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I SEQUOYAH - UNIT 2 B 3/4 4-15 Amendment No. 106, 120 1