ML20003C737
| ML20003C737 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/06/1981 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003C738 | List: |
| References | |
| NUDOCS 8103180110 | |
| Download: ML20003C737 (11) | |
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UNITED ST ATEs NUCLEAR REGULAlORY COMMISSION 5
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT, UNIT 1 Af!ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) having found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77, filed by the Tennessee Valley Authority (licensee), dated December 31, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with.the license, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 ha conducted in compliance with the Comission'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 a:cordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been 'sati sfied.
- 2.. Accordingly, the license is hereby ar, ended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as.follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 4, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amended license is effective as of March 6,1981.
FOR THE NUCLEAR REGULATORY COMMISSION
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A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance:
March 6,1981 l
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 4 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix 'A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical' lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Overleaf Amended Page Page 3/4 6-25 3/4 6-26 3/4 6-28 3/4 6-27 B3/4 6-3 B3/4 6-4 t
1 SEQUOYAH---UNIT 1 l
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CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS - W LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.
.AFPLICABILITY: MODES 1 and 2.
ACTION:
With one hydrogen recombiner system inoperable, restore the inoperable system to OPFRABLE status within 30 days or 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 />.
SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:
At least once per 6 months by verifying during a recombiner system a.
functional test that the minimum heater sheath temperature increases togreaterthanorequalto700*Fwithin90 minutes. Upon reaching 700 F, increase the power setting to maximum power for 2 minutes and verify that the power meter reads greater than or equal to 60 KW.
b.
At least once per 18 months by:
1.
Performing a CHANNEL CALIBRATION of all recombiner instrumenta-tion and control circuits, 2.
Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure (i.e.,
loose wiring or structural connections, deposits of foreign materials,etc.),and 3.
Verifying the. integrity of all heater electrical circuits by performing a resistance to ground test following the abose required functional test.
The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.
SEQUOYAH - UNIT 1 3/4 6-25
I CON [AINMENTSYSTEMS 3/4.6.5 ICE CONDENSER ICE BED LIMITING CONDITION FOR OPERATION 3.6.5.1.
The ice bed shall be OPERABLE with:
The stored ice having a boron concentration of at least 1800 ppm a.
boron as sodium tetraborate and a pH of 9.0 to 9.5, b.
Flow channels through the ice condenser, A maximum ice bed temper'ature of less than or equal 27'F, c.
d.
A total ice weight of at least 2,333,100 pounds at a 95% level of confidence, and e.
1944 ice baskets.
APPLICABILITY. MODES 1, 2, 3 and 4.
ACTION:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- SURVEILLANCE REOUIREMENTS 4.6.5.1 The ice condenser shall be determined OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using the ice bed temperature monitoring a.
system to verify that the maximum ice bed temperature is less than or equal to 27 F.
b.
At least once per 6 months during the first 2 years following initial criticality and at least once per 12 months thereaf ter by:
l 1.
Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration of at least 1800 ppm as sodium tetraborate and a pH of 9.0 to 9.5 at 20*C.
R 2.
Weighing a representative sample of at least 144 ice' baskets and verifying that each basket contains at least 1200 lbs of ice. The representative sample shall include 6 baskets from each of the 24 ice condenser bays and shall be constituted of 1
5EQUOYAH - UNIT 1 3/4 6-26
' AMENDMENT NO.4
CONTAlf4 MENT SYSTEMS 3/4.6.5 ICE CONDENSER ICC OED LIMITIflG CONDITION FOR OPERATION 3.6.5.1 The ice bed shall be OPERABLE with:
The stored ice having a baron concentration of at least 1800 ppm a.
boron as sodium tetraborate and a pH of 9.0 to 9.5, b.
Flow channels through the ice condenser, c.
A maximum ice bed temper'ature of less than or equal 27 F, d.
A total ice weight of at least 2,333,100 pounds at a 95% level of confidence, and e.
1944 ice baskets.
APPLICABILITY. MODES 1, 2, 3 and 4.
ACTION:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY wii.hin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- SURVEILLANCE REQUIREMENTS 4.6.5.1 The ice condenser shall be determined OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using the ice bed temperature monitoring system to verify that the maximum ice bcd temperature is less than or equal to 27 F.
b.
At least once per 5 months during the first 2 years following initial j
. criticality and at least once per 12 months thereaf ter by:
1.
Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration of at least l
1800 ppm as sc ium tetraborate and a pH of 9.0 to 9.5 at 20 C, 2.
Weighing a representative sample of at least 144 ice baskets l
and verifying that each basket contains at least 1200 lbs of ice.
The representative sample shall include 6 baskets from each of the 24 ice condenser bays and shall be constituted of i
SEQUOYAH - UNIT 1 3/4 6. AMENDMENT NO.4 l'
CONTAthPENT SYSTEPS SURVEILLANCE REOUIREPENTS (Continuedl one basket each from Padial Pows 1, 2, 4, 6, 8 and 0 for from the same row of an ad.facent bay if a basket from a designated row cannot be obtained for weighing) within each bay.
If any basket is found to contain less than l_200_ pounds of ice, a representative sample of 20 additional baskets from the same bay shall be weighed. The minimum averace weight of ice from the 20 additional baskets and the discrepant basket shall not be less than.1200 pounds / basket at a 95% level of confidence.
The ice condenser shall a o be subdivided into 3 groups of baskets, as follows: Group 1 - bays 1 through 8. Group'2 -
bays 9 throuch 16, and Group 3 - bays 17 through 24 The minimum average ice weight of the sanple baskets from Radial Rows 1, 2, 4, 6, 8 and 9 in each group shall not be less than 1200 pounds / basket at a 95% le,el of confidence.
The ninfrun total ice condenser ice weight at a 05% level of confidence shall be calculated using all ice basket weights detennined during this weighing program and shall not be less than 2.333,100 pounas.
3.
Verifying, by a visual inspection of at least two flow passaces per ice condenser bay, that the accumulation of frost or ice on flow passaces between ice baskets, past lattice frames 3 throuch the interrediate and top deck floor gratino, or past the lower inlet olenun succort structures and turnino vanes is restricted to a thickness of less than or enual to 0.3R inches.
If one flow passane per hay is found to have an accumulation of frost or ice with a thickness nf greater than or ecual to 0.38 inches, a representative sample of 20 additional flow passages from the same bay shall be visually inspected.
If these additional flow l
passaces are'forind acceptable, the surveillance program nay proceed considering the single deficiency as unfoue and acceptable.
Fore tnan one restricted flow passage per bay.is evidence of abnormal degradation of the ice condenser.
I At least once oer 40 renths by liftino and visually. inspecting the c.
accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verifyino that the ice baskets are free of detrinental structural wear, cracks, corrosion or other 1amace. The ice baskets shall be raised at least 10 feet for this \\nspection.
SE0l!0YAH - UNIT 1
.3/4 6-27 AMENDMENT NO. 4 9
CONTAINMENT SYSTEMS ICE BED TEMPERATURE MONITORING SYSTEM -
LIMITING CONDITION FOR OPERATION 3.6.5.2 The ice bed temperature monitoring system shall be OPERABLE with at least 2 OPERABLE RTD channels in the ice bed at each of 3 basic elevations (10'6", 30'9" and 55' above the floor of the ice condenser) for each one third of the ice condenser.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With the ice bed temperature monitoring system inoperable, POWER OPERATION may continue for up to 30 days provided:
1.
The ice compartment lower inlet doors, intermediate deck doors, and top deck doors are closed; 2.
The last recorded mean ice bed temperature was less than or equal to 20 F and steady; and 3.
The ice condenser cooling system is OPERABLE with at least:
a) 21 OPERABLE air handling units, b) 2 OPERABLE glycol circulating pumps, and c) 3 OPERABLE refrigerant units; otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With the ice bed temperature monitoring system inoperable and with the ice condenser cooling system not satisfying the minimum components OPERABILITY requirements of a.3 above, POWER OPEPATICN may continue for up to 6 days provided the ice compartment lower inlet doors, intermediate deck doors, and top deck doors are closed and the last recorded mean ice bed temperature was less 'than or equal to 15*F and steady; otherwise, be in at least HOT STAND 8Y within the next 6-hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.2 The ice bed temperature monitoring system shall be determined OPERABLE-by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SEQUOYAH - UNIT 1 3/4 6-28
CONTAINMENT SYSTEMS i
BASES 3/4.6.1.8 EMERGENCY GAS TREATMENT SYSTEM (EGTS)
The OPERABILITY of the EGTS cleanup subsystem ensures that during LOCA conditions, containment vessel leakage into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere.
This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radiation doses to within
'the limits of 10 CFR 100 during LOCA conditions.
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 suf ficient to reduce the buildup of moisture on the absorbers and HEPA filters.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM Use of the containment purg.. lines is restricted to only one pair (one supply line and one exhaust line) of purge system lines at a time to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss of coolant accident during purging operations.
The analysis of this accident assumed purging through the largest pair of lines (a 24 inch inlet line and a 24 inch outlet line), a pre-existing iodine spike in the reactor coolant and four second valve closure times.
t 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ehsures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside envirnnment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment wil! be consistent with the assumptions used in the analyses for a LOCA.
J/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to caintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit or the purge system SEQUOYAH UNIT I B 3/4 6.
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CONTAINMENT SYSTEMS BASES 3/4.6.1.8 EMERGENCY GAS TREATMENT SYSTEM (ECTS)
The OPERABILITY of the EGTS cleanup subsystem ensures that during LOCA conditions, containment vessel leakage into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere.
This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radiation doses to within the limits of 10 CFR 100 durisJ LOCA conditions.
Cumulative operation of the system with the heaters on f.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 anisture on the absorbers and HEPA filters. ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM Use of the containment purge lines is restricted to only one pair (one supply line and one exhaust line) of purge system lines at a time to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss of coolant accident during purging operations.
The analysis of this accident assumed purging through the largest pair of lines (a 24 ir.ch inlet line and a 24 inch outlet line), a pre-existing iodine spike in the reactor coolant and four second valve closure times.
3/4.6.2 DEPRESSURllATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENf SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OFERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
J/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrcqen gas ensures that this equipment will be available to caintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit or the purge system SEQUOYAH - UNIT 1 B 3/4 6-3
CONTAINMENT SYSTEMS BASES is capable of controlling the expected hydrogen generation associated with 1) zirconium water reactions, 2) radiolytic decomposition of water and 3) corro-sion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA", March 1971.
The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent localized accumulations of hydrogen from' exceeding the flammable limit.
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3/4.G.5 ICE CONDENSER The requirements associated with each of the components of the ice con-denser ensure that the overall system will be available to provide sufficient
. pressure suppression capability to limit the containment peak pressure tran-sient to less than 12 psig during LOCA conditions.
3/4.6.5.1 ICE BE0 Th'e OPERARILITY of the ice bed ensures that the required ice inventory will 1) be distributed evenly through the containment bays, 2) contain suf fi-cient baron to preclude dilution of tne containment sump following the LOCA and 3) contain suf ficient heat removal capability to condense the reactor system volume released during a LOCA. These conditions are consistent with the assumptions used in the accident analyses.
L The minimum weight figure of 1200 pounds of ice per basket contains a 10%
conservative allowance for ice loss through sublimation which is a factor of
- 10. higher than assumed for the ice condenser design. The minimum weight figure of 2.333.100 pounds of ics also contains an additional L% conservative allowance to account for systematic error in weighing instruments.
In the event that observed sublimation rates are equal to or lower than design predic-tions after three years of operation, the minimum ice baskets weight may be adjusted downward.
In addition,-the number of ice baskets requirad to be nweigned each 9 months may be recuted af ter 3 years of operation if such a r~ duction is supported by observed sublimation data.
3/4.6.
" ICE BED TEMPERATURE MONITORING SYSTEM The OPERABILITY of the ice bed temperature monitoring system ensures that
~the capability is available for monitoring the ice temperature.
In the event the monitoring system is inoperable, the ACTION requirements provide' assurance
-that-the ice bed heat removal capacity will.be retained within the specified-time limits.
E SEQUOYAH - UNIT 1 B 3/4 6-4 AMENDMENT NO. 4 1
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