ML20248L191
| ML20248L191 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/08/1998 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248L194 | List: |
| References | |
| NUDOCS 9806100488 | |
| Download: ML20248L191 (14) | |
Text
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p nciruqk UNITED STATES p
4,5 j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 30666-0001
.....l TENNESSEE vat i FY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
232 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 I
Energy Act of 1954, as amended (the Act), and the Commission's rules and I
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 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.
9806100488 980608 PDR ADOCK 05000327 P
~
2-2.
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 I
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. 232 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 4
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 Issuance:
June 8,1998 i
ATTACHMENT TO LICENSE AMENDMENT NO. 232 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technl cal 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 Vill index page Vill 3/4 7-10a (new page)
B 3/4 7-3 B 3/4 7-3 B 3/4 7-3a (new page )
l l
IlEEK LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION FAQX 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS 3/4 6-24 ELECTRIC HYDROGEN RECOMBINERS - W.
3/4 6-25 HYDROGEN MITIGATION SYSTEM 3/4 6-25a lR217 3/4.6.5 ICE CONDENSER ICE BED.
3/4 6-26 ICE BED TEMPERATURE MONITORING SYSTEM.
3/4 6-28 ICE CONDENSER DOORS 3/4 6-29 INLET DOOR POSITION MONITORING SYSTEM.
3/4 6-31 DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EQUIPMENT NATCHES 3/4 6-32 CONTAINMENT AIR RETURN FANS.
3/4 6-33 FLOOR DRAINS 3/4 6-34 REFUELING CANAL DRAINS 3/4 6-15 DIVIDER BARRIER SEAL 3/4 6-36 3/4.6.6 VACUUt1 RELIEF LINES.
3/4 6-38 lR201 3 /4. 7 PLANT SYSTEMS 3/4.7.1 TURBINE Q CLE
~
SArETY VALVES.
. 3/4 7-1 AUXILIARY FEEDWATER SYSTEM 3/4 7-5 CONDENSATE STORAGE TANK.
3/4 7-7 ACTIVITY 3/4 7-e MAIN STEAM LINE ISOLATION VALVES 3/4 7-10 MAIN FEEDWATER ISOLATION, REGULATING, AND BYPASS VALVES
.3/4 7-10a l
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.
3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM-3/4 7-12 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM 3/4 7-13 l
SEQUOYAH --UNIT 1 VIII Amendment No. 116, 197, 232 i
l' L.
PLANT SYSTEMS MAIN FEEDWATER ISOLATION, REGULATING, AND BYPASS VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 Four main feedwater isolation valves (MFIVs), four main feedwater regulating valves (MTRVs), and four MFRV bypass valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3 ACTION:
a.
With one or more MFIVs inoperable, POWER OPERATION may continue provided the inoperable valve is returned to OPERABLE status or closed or isolated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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.
With one or more MFRVs inoperable, POWER OPERATION may continue provided the inoperable valve is returned to OPERABLE status or closed or isolated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.
c.
With one or more MFRV bypass valves inoperable, POWER OPERATION may continue provided the inoperable valve is returned to OPERABLE status or closed or isolated within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />st otherwise, be in at least HOT l
STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SEUTDCWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
I d.
For each MFIV, MFRV, or MFRV bypass valve that has been clo&2d or isolated to satisfy Action a.,
b.,
or c. above, verify that it is 4
closed or isolated once per 7 days, e.
With two valves in the same main feedwater flow path inoperable, isolate the affected flow path within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise, be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.
f.
Separate entry into the above ACTIONS is allowed for each valve or flow path. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.6 In addition to the requirements of Specification 4.0.5, verify each MFIV, MFRV, and MFRV bypass valve closes on an actual or simulated automatic actuation signal at least once per 18 months.
l l
SEQUOYAH - UNIT 1 3/4 7-10a Amendment No. 232 1
1
f l
l PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the accident analyses.
1 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the. pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
3 /4. 7.1. 6 MAIN FEEDWATER ISOLATION, REGULATING, AND BYPASS VALVES Isolation of the main feedwater (MFW) system is provided when required to mitigate the consequences of a steam line break, feedwater line break, excessive feedwater flow, and loss of normal feedwater (and station blackout) accident. Redundant isolation capability is provided on each feedwater line consisting of the feedwater isolation valve (MFIV) ard the main feedwater regulating valve (MFRV) and its associated bypass valve. The safety function of these valves in fulfilled when closed or isolated by a closed manual isolation valve. Therefore, the feedwater isolation function may be considered OPERABLE if its respective valves are OPERABLE, if they are maintained in a closed and deactivated position, or if isolated by a closed manual valve. The 72-hour completion time to either restore, close, or isolate an inoperable valve takes into account the redundancy afforded by the remaining OPERABLE valves and the low probability of an event occurring that would require isolation of the MFW flow paths during this time period. The 8-hour completion time for two inoperable valves in one flow path takes into account the potential for no redundant system to perform the required safety function and a reasonable duration to close or isolate the flow path. Although the steam generator can be isolated with the failure of two valves in parallel, the double failure could be an indication of a common mode failure and should be treated the same as the loss of the isolation function. The 7-day frequency to j
verify that an inoperable valve is closed or isolated is reasonable based on valve status indications available in the control room, and other administrative controls to ensure the valves are closed or isolated.
I 1
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATIOT The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum lBR allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on a steam generator RT f 25'F and are sufficient to NDT prevent brittle fracture I
SEQUOYAH - UNIT 1 B 3/4 7-3 Amendment No. 232 1
1 1
PLANT SYSTEMS l
BASES 3/#.7.1 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety
[
related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3 /4. 7. 4 ESSENTIAL RAW COOLING WATER SYSTEM R16 The OPERABILITY of the essential raw cooling water system ensures that l
sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling l
capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
SEQUOYAH - UNIT 1 5 3/4 7-3a Amendment No. 12, 232
p5 *to y*
t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20655-0001 f
<n TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 222 License No. DPR-79
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Tennessee Valley Authority (the licensee) dated l
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; D.
The issuance of thic 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 a!i applicable requirements have been satisfied.
. 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 l
The Technical Specifications contained in Apper: dices A and B, as revised through Amendment No. 222
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective es of its date of issuance, to be implemented no later than 45 days afterissuance.
FOR THE NUCLEAR REGULATORY COMMISSION n.e L
c s
Frederick J. Hebdon, irector Project Directorate ll-3 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date oflasuance: June 8,1998 h
_m_____.______2_
l t
L ATTACHMENT TO LICENSE AMENDMENT NO. 222 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 marginal lines indicating the area of change.
REMOVE INSERT Index page Vill Index page Vill 3/4 7-10a (new page)
B 3/4 7-3 8 3/4 7-3 B 3/4 7-3a (new page)
I
~ - _ - _ -
IIEEK LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION R&QE 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS.
3/4 6-24 ELECTRIC HYDROGEN RECOMBINERS - W.
3/4 6-25 HYDROGEN MITIGATION SYSTEM 3/4 6-26 lR203 3/4.6.5 ICE CONDENSER j
i ICE BED.
3/4 6-27 ICE BED TEMPERATURE MONITORING SYSTEM.
3/4 6-29 j
ICE CONDENSER DOORS.
3/4 6-30 INLET DOOR POSITION MONITORING SYSTEM.
3/4 6-32 DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EQUIPMENT HATCHES.
3/4 6-33 CONTAINMENT AIR RETURN FANS.
3/4 6-34 l
FLOOR DRAINS 3/4 6-35 i
REFUELING CANAL DRAINS 3/4 6-36 DIVIDER BARRIER SEAL 3/4 6-37 3/4.6.6 VACUUM RELIEF VALVES 3/4 6-39 lR188 3/4.7 PLANT SYSTEMS.
3/4.7.1 TURBINE CYCLE SAFETY VALVES.
3/4 7-1 AUXILIARY FEEDWATER SYSTEM
. 3/4 7-5 CONDENSATE STORAGE TANK.................
3/4 7-7 ACTIVITY
. 3/4 7-8 MAIN STEAM LINE ISOIATION VALVES 3/4 7-10 MAIN FREDWATER ISOIATION, REGULATING, AND BYPASS VALVES 3/4 7-10a l
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.
3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4 7-12 SEQUOYAH - UNIT 2 VIII Amendment No. 188, 203, 222
J PLANT SYSTEMS j'
. man Fmw%TER ISOIATION. REGULATING. AND BYPASS VALVES LIMITING CONDITION FOR OPERATION 327..'116 Four main feedwater isolation valves-(MFIVs), four main feedwater
, regulating valves (MFRVs), and four MFRV bypass valves shall be
' OPERABLE.
APPLICABILITY: MODES 1, 2, and 3 ACIIQH:
With one or more MFIVs1 inoperable,. POWER OPERATION may continue-a.
provided the inoperable valve is returned to OPERABLE status or closed or isolated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be-in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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.
With one or more MTRVs inoperable, POWER OPERATION may continue provided the inoperable valve is returned to OPERABLE status or closed or isolated within 72 houras otherwise, be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.
With one'or more MFRV bypass valves inoperable, POWER OPERATION may c.
continue provided the inoperable valve is returned to OPERABLE status or closed or isolated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STANDBY within the next 6' hours and in NOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
For each MFIV, MFRV, or MFRV bypass valve that has been closed or isolated to satisfy Action a.,
b.,
or c. above, verify that it is closed or isolated once per 7 days.
With two valves in the same-main feedwater flow path inoperable, a.
isolate the affected flow path within a hours; ock.erwise, be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.
j f.
Separate entry into the above ACTIONS is allowed for each valve or
-flow path. The provisions of Specification 3.0.4 are not applicable.
4 SURVEILLANCE REQUIREMENTS
'4.7.1.6 In addition to the requirements of Specification 4.0.5, verify each MFIV, MFRV, and MFRV bypass valve closes on an actual or simulated automatic actuation signal at least once per 18 months.
'SEQUOYAM - UNIT 2 3/4 b 10m.
Amendment No. 222
t.?
.i PLANT SYSTEMS
~ BASES :
1/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant.off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam
. generator of the affected steam line.' These values are consistent with the assumptions used in the accident analyses.
3/4.7.1.5 MAIN STEAM LINE ISOIATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more-than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to il minimize the positive reactivity offacts of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent
-with the assumptions used in the accident analyses.
3 /4. 7.1. 6 MAIN FEEDWATER ISOLATION. REGULATING. AND BYPASS VALVES l
. Isolation of the main feedwater (MFW) system is provided when required to mitigate the consequences of a steam line break, feedwater line break,
' excessive feedwater flow, and loss of normal feedwater (and station Elackout) accident. Redundant isolation capability is provided on each feedwater line consisting of the feedwater isolation. valve (MFIV) and the main feedwater regulating valve (MFRV) and its associated bypass valve. The safety function of these valves is fulfilled when closed or isolated by a closed manual isolation valve. Therefore, the feedwater isolation function may be considered OPERABLE if its respective valves are OPERABLE, if they are maintained in a closed and deactivated position, or if isolated by a closed manual valve. The 72-hour completion time to either restore, close, or isolate an inoperable valve takes into account the redun/,ancy afforded by the remaining OPERABLE valves and the low probability of an event occurring that would require isolation of the MFW flow paths during this time period.. The 8-hour completion time for two inoperable valves in one flow path takes into account the potential:for no redundant system to perform the required safety function and a reasonable duration to close or isolate the flow path. Although the steam generator can be isolated with the failure of two valves in parallel, the double failure could be an indication of a common mode failure and should-be treated the same as the loss of the isolation function. The 7-day frequency to verify that an inoperable valve is closed or isolated is reasonable based on valve status indications available in the control room, and other administrative controls to ensure the valves are closed or isolated.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION L
The limitation on steam generator pressure and temperature ensures that
.the pressure induced stresses in the steam generators do not exceed the maximum l
allowable fracture toughness stress limits. The limitations of 70*F and 200 peig are based on a steam generator RT of 25'F and are sufficient to prevent BR NDT brittle' fracture.
l l
'i SEQUOYAN. UNIT 2 3 3/4 7-3 Amendment No. 222 r
(,b
7-.___.____
.--__. _ _ _ _ _ _ - _.___ _ __-_.--. _-=-_. _,. _ _ _ __ _ __ ___-._ ____--____..
PLANT SYSTEMS BASES-3/4.7.3 CM e-1 COOLTNG WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM The OPERABILITY of the essential raw cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
i l
l smoooYAu - uuIT 2 m 3/4 7-3.
Amendment No. 222
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- _ _ = -
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