ML20052F733
| ML20052F733 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/04/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052F734 | List: |
| References | |
| NUDOCS 8205130538 | |
| Download: ML20052F733 (40) | |
Text
N TENNESSEE VALLEY AUTHORITY DOCVET H0. 50-327 SEQUOYAH NUCLEAR PLAMT, UtlIT 1 AMENDPENT TO FACILITY OPERATIMG LICENSE Anendrent No. 13 License Ho. OPR-77 1.
The Huclear Regulatory Connission (the Connission) having found that:
A.
The applications for amendment to the Sequoyah Huclear Plant, Unit 1 (tbe facility) Facility Operating License No. OPR-77 filed by the Tennessee Valley Authority (licensee), dated December 10, 1981 (two letters), March 1, March 9, and April 7,1902, conply with the stand-ards and requirenents of the Atomic Enercy Act of 1954, as anended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; n.
The facility will operate in confornity with the license, as amended, the provisions of the Act, and the rules and regulations of the Con-nission; C.
There is reasonable assurance (1) that the activities authorized by this anendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D.
The issuance of this amendment will not be ininical to the co7 mon defense and security or to the health and safety of the public; and E.
The issuance of this anend-ent is in accordance with 10 CFR Part 51 of the Coonission's regulations and all applicable requirements have been satisfied, v t'J C.
2.
Accordingly, the license is hereby anended by page changes to the Appendix A co Technical 59ecifications as indicated in the attachnents to this license anent-SS nent and paracraoh 2.C.(2) of Facility Operating License No. DPR-77 is hereby O
anended to read as follows:
e cua (2) Technical Specifications CS g
The Technical Specifications contained in Appendix A, as revised ro o through keendnent Mo.13, are hereby incorporated into the license.
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, The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendrent is effective as of its date of issuance.
FOR THE fiUCLEAR REGULATORY COMMISSION g
i Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A lechnical Specificotion Changes Date of issuance: May 4, 1982 l
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ATTACHMDIT TO LICENSE AMEN 0HENT NO.13 FACILITY OPERATING LICENSE NO. DPR-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 Amendnent number.and contain vertical lines indicating the area of change. The corresponding over-leaf pages are also provided to maintain document completeness.
Overleaf Amended Pace Page 1-8 3/4 3-37 3/4 3-73 3/4 3-80 3/4 6-19 3/4 6-20 3/4 6-28 3/4 7-21 3/4 7-31 3/4
'i-37 3/4 7-38 3/4 7-39 3/4 7-40 3/4 12-9 3/4 12-10 5-5 6-15 6-15a 5-3 5-4 In order to clarify changes made in Amendnent No.12, please delete the fol-lowing pages:
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DEFINITIONS TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY 5
At least once per 12' hours.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D W
At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
J SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to each release.
N.A.
Not applicable.
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SEQUOYAH - UNIT 1 1-8 Amendment No. 12
TABLE 4.3-2 (Continued)
~
IE ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SE SURVEILLANCE REQUIREMENTS SE CHANNEL MODES IN WHICH E
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE Z
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED c.
Main Steam Generator Water S
R M
1,2,3 Level-Low-Low d.
S.I.
See 1 above (all SI surveillance requirements) e.
Station Blackout N.A.
R N.A.
1,2,3 f.
Trip of Main Feedwater N.A.
N.A.
R 1, 2 Pumps g.
Auxiliary feedwater Suction N.A.
R M
1,2,3 Pressure - Low ki 7.
LOSS OF POWER w
a.
6.9 kv Shutdown Board g
Undervoltage 1.
Loss of Voltage S
R M
1,2,3,4 2.
Load Shedding S
R N.A.
1,2,3,4 8.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.
Pressurizer Pressure, N.A.
R (4)
N.A.
1,2,3 P-11
)>
N.A.
R (4)
N.A.
1,2,3 j
D.
Tavg, P-12 E
c.
Steam Generator N.A.
R (4)
N.A.
1, 2 Level, P-14 e
E 9.
AUTOMATIC SWITCH 0VER TO CONTAINMENT SUMP a.
RSWT Level - Low S
R M
1,2,3,4 COINCIDENT WITH Containment Sump Level - High S
R M
1,2,3,4 AND Safety Injection (See 1 above for all Safety Injection Surveillance Requirements)
INSTRUMENTATION TABLE 4.3.8 (Continued)
TABLE NOTATION During liquid additions to the tank.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Downscale failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Downscale feilure.
(3) The initial CHANNEL CALIBRATION shall be perfo>med using one or more of the reference standards certified by the National L'ureau of Standards or using standards that have been obtained from suppliers that participate in measure-ment assurance activities with NBS.
These standards shall permit calibrat-ing the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, period.ic, or batch releases are made.
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SEQUOYAH - UNIT 1 3/4 3-73 Amendment No. 13 I
t INSTRUMENTATION TABLE 4.3-9 (Continued)
TABLE NOTATION At all times.
During waste gas disposal system operation.
During shield building exhaust system operation.
During waste gas releases.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
' 1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
(2) The CHANNEL FUNCTION TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Downscale failure.
(3) The initial CHANNEL CALIBRATION sha'l be performed using one or more of the reference standards certified by tre National Bureau of Standards or using standards that have been obtained from suppliers that participate in measure-ment assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For sub-sequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples contain-ing a nominal:
1.
One volume percent hydrogen, balance nitrogen and 2.
Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples l
containing a nominal:
1.
One volume percent oxygen, balance nitrogen, and 2.
Four volume percent oxygen, balance nitrogen.
SEQUOYAH - UNIT 1 3/4 3-80 Amendment No. 13
TABLE 3.6-2 jE CONTAINMENT ISOLATION VALVES S
E VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) h A.
PHASE "A" ISOLATION 5
1.
FCV-1-7 SG Blow Dn 10 2.
FCV-1-14 SG' Blow Dn 10 3.
FCV-1-25 SG Blow Dn 10 4.
FCV-1-32 SG Blow Dn 10 5.
FCV-1-181 SG Blow Dn 15 6.
FCV-1-182 SG Blow Dn 15 7.
FCV-1-183 SG Blow Dn 15 8.
FCV-1-184 SG Blow Dn 15 9.
FCV-31C-222 CW-Inst Room Clrs 10 10.
FCV-31C-223 CW-Inst Room'Cirs 10 11.
FCV-31C-224 CW-Inst Room Clrs 10 12.
FCV-31C-225 CW-Inst Room Cirs 10 R'
13.
FCV-31C-229 CW-Inst Room Clrs 10 14.
FCV-31C-230 CW-Inst Room Clrs 10 T
15.
FCV-31C-231 CW-Inst Room Clrs 10 g
16.
FCV-31C-232 CW-Inst Room Clrs 10 17.
FCV-43-22 Sample RC Outlet Hdrs 10 18.
FCV-43-23 Sample RC Outlet Hdrs 10 19.
FCV-43-55 SG Blow Dn Sample Line 10 20.
FCV-43-58 SG Blow Dn Sample Line 10 21.
FCV-43-61 SG Blow Dn Sample Line 10 22.
FCV-43-64 SG Blow Dn Sample Line 10 23.
FCV-61-96 Gylcol Inlet to Floor Cooler 30 y
24.
FCV-61-97 Gylcol Inlet to Floor Cooler 30 g
25.
FCV-61-110 Gylcol Outlet to Floor Cooler 30 Et 26.
FCV-61-122 Gylcol Outlet to Floor Cooler 30 g
27.
FCV-61-191 Ice Condenser - Gylcol In 30 r*
28.
FCV-61-192 Ice Condenser - Gylcol In 30 g
29.
FCV-61-193 Ice Condenser - Gylcol Out 30 30.
FCV-61-194 Ice Condenser - Gylcol Out 30
[
31.
FCV-62-61 RCP Seals 10 l
TABLE 3.6-2 (Continued)
E S
CONTAINMENT ISOLATION VALVES E
VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)
A.
PHASE "A" ISOLATION (Cont.)
32.
FCV-62-63 RCP Seals 10 33.
FCV-62-72 Letdown Line' 10 34.
FCV-62-73 Letdown Line 10 35.
FCV-62-74 Letdown Line 10 36.
FCV-62-77 Letdown Line 10 37.
FCV-63-23 Accum to Hold Up Tank 10 38.
FCV-63-64 WDS N to Accum 10 2
39.
FCV-63-71 c.ccum to Hold Up Tank 10 40.
FCV-63-84 Accum to Hold Up Tank 10 41.
FCV-68-305 WDS N to PRT 10 42.
FCV-68-307 PRTtbGasAnalyzer 10 t'
43.
FCV-68-308 PRT to Gas Analyzer 10 44.
FCV-70-85 CCS from Excess Lt Dn Hx 10 T
45.
FCV-70-143 CCS to Excess Lt Dn Hx 60 46.
FCV-77-9 RCDT Pump Disch 10 47.
FCV-77-10 RCDT Pump Disch 10 48.
FCV-77-16 RCDT to Gas Analyzer 10 49.
FCV-77-17 RCDT to Gas Analyzer 10 50.
FCV-77-18 RCDT and PRT to V H 10 51.
FCV-77-19 RCDT and PRT to V H 10 52.
FCV-77-20 N to RCDT 10 53.
FCV-77-127 F$oorSumpPumpDisch 10 g
54.
FCV-77-128 Floor Sump Pump Disch 10 g
55.
FCV-81-12 Primary Water Makeup 10 g
56.
FCV-87-7 UHI Test Line 10 g
57.
FCV-87-8 UHI Test Line 10 58.
FCV-87-9 UHI Test Line 10 g
59.
FCV-87-10 UHI Test Line 10 60.
FCV-87-11 UHI Test Line 10 g
61.
FCV-26-240 Fire Protection Isol.
20 62.
FCV-26-243 Fire Protection Isol.
20
C0t4TAINMENT SYSTEMS ICE BED TEMPERATURE MONITORING SYSTEM LIMI. TING 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 indication not available in the main control room, determine the ice bed temperature at the local ice condenser temperature monitoring panel every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b.
With the ice bed temperature monitoring system inoperable, and unable to determine ice bed temperature at the local panel, POWER OPERATION may continue for up to 30 days provided:
1.
.The ice compartment lower inlet doors, intermediate deck doors, and to? 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,
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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 />.
I b.
With the ice bed temperature monitoring system inoperable and unable to determine the ice bed temperatures by alternate means and with the ice condenser cooling system not satisfying the minimum components OPEi' ABILITY requirements of a.3 above, POWER OPERATION 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 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 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 Amendment No. 13
PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9.
All safety-related snubbers shall be OPERABLE.
The snubbers are shown in Tables 4.7.9.a and 4.7.9.b and are listed in Surveillance Instruction SNP SI-162.
Any exemptions to the surveillance program are shown in Table.4.7.9.c and in SNP SI-162.
APPLICABILITY:
MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems or partial systems required OPERABLE in those MODES.)
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9.
Each safety-related snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
These snubbers are shown in Tables 4.7.9.a and 4.7.9.b, and are listed in Surveillance Instruction SNP SI-162.
Table 4.7.9.b is a detailed tabulation of the hydraulic snubbers which are also shown in Table 4.7.9.a.
Any exemption to any portion of the surveillance program for any snubber is shown in Table 4.7.9.c.
a.
Inspection Groups The snubbers may be categorized into two major groups based on whether the snubbers are accessible or inaccessible during reactor operation.
These major groups may be further subdivided into subgroups based on design, environment, or other features which may be expected to affect the OPERABILITY of the snubbers within the subgroup.
Each subgroup or group may be inspected independently in accordance with 4.7.9.b through 4.7.9.h.
b.
Visual Inspection Schedule and Lot Size The first inservice visual inspection of snubbers shall be completed by October 31, 1981, and shall include all snubbers on safety-related systems.
If less than two (2) snubbers are found inoperable duning the first inservice visual inspection, the second inservice visual inspection shall be performed 18 months 25% from the date of the first inspection or during an outage of sufficient duration (at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in Mode 5).
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
SEQUOYAH - UNIT 1 3/4 7-21 Amendment No. 13
PLANT SYSTEMS ACTION:
(Continued) c)
In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.7'.11.1 The fire suppression water system shall be demonstrated OPERABLE:
At least cace per 31 days on a STAGGERED TEST BASIS by starting each a.
electric motor driven pump and operating it for at least 15 minutes on recirculation flow.
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.
- c.
At least once per 6 months by performance of a system flush.
d.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
At least once per 18 months by performing a system functional test e.
which includes simulated automatic actuation of the system throughout its operating sequence, and:
1.
Verifying that each automatic valve in the flow path actuates to'its correct position, 2.
Verifying that each pump develops at least 1174 gpm at a system head of 312 feet, 3.
Cycling each valve in the flow path that is not testable during plant operation through at least one complete.ycle of full travel, and 4.
Verifying that the No. 1 fire pump starts to maintain the fire suppression water system pressure greater than or equal to 125 psig and that the No. 2 fire pump also starts automatically within 10 + 2 seconds when the fire suppression water system is not maintained greater than or equal 'to 125 psig by the No.1 pump, f.
At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
^ Note:
These flushes should coincide with the chlorination of the raw service and fire suppression water system.
These flushes should be run, one between April 1 and June 30, and the other~between September 1 and November 15.
Within the prescribed spring and fall test period, deviation from the six-month performance frequency is authorized.
SEOCOYAH - UNIT 1 3/4 7-31 Amendment No. 13
PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.
APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.
ACTION:
a.
With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any cther report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the station to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:
a.
At least once per 31 days by visual inspection of the stations accessible during plant operations to assure all required equipment is at the station.
b.
At least once per 18 months by:
1.
Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station, 2.
Removing the hose for inspection and re-racking, and 3.
Inspecting all gaskets and replacing any degraded gaskets in the couplings.
c.
At least once per 3 years by:
1.
Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
2.
Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.
SEQUOYAH - UNIT 1 3/4 7-37 Amendment No.13 w-,
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PLANT SYSTEMS TABLE 3.7-5 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
a.
Reactor Building - Annulus Area Platform 778.5 1-26-1196 Platform 778.5 1-26-1197 Platform 778.5 1-26-1198 Platform 778.5 1-26-1199 Platform 759.5 1-26-1200 Platform 759.5 1-26-1201 Platform 759.5 1-26-1202 Platform 759.5 1-26-1203 Platform 740.5 1-26-1204 Platform 740.5 1-26-1205 Platform 740.5 1-26-1206 Platform 740.5 1-26-1207 Platform 721.5 1-26-1208 Platform 721.5 1-26-1209 Platform 721.5 1-26-1210 Platform 721.5 1-26-1211 Platform 701.5 1-26-1212 Platform 701.5 1-26-1213 Platform 701.5 1-26-1214 Platform 701.5 1-26-1215 Platform 679.78 1-26-1216 Platform 679.78 1-26-1217 Platform 679.78 1-26-1218 Platform 679.78 1-26-1219 b.
Reactor Building - RCP & Lower Containment Air Filters Area Reactor Building 679.78 1-26-1220 Reactor Building 679.78 1-26-1221 Reactor Building 679.78 1-26-1222 Reactor Building 679.78 1-26-1223 Reactor Building 679.78 1-26-1224 Reactor Building 679.78 1-26-1225 c.
Control Building Control Building 732 0-26-1186 Control Building 732 0-26-1191 Control Building 706 0-26-1187 Control Building 706 0-26-1192 l
SEQUOYAH - UNIT 1 3/4 7-38 Amendment No.13
o TABLE 3.7-5 (Continued)
FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
Control Building 685 0-26-1188 Control Building 685 0-26-1193 Control Building 669 0-26-1189 Control Buildirig 669 0-26 '194 d.
Diesel Generator Building Corridor 722 0-26-1077 Corridor 740.5 0-26-1080 Air Exhaust Rm.
0-26-1082 e.
Additional Equipment Building - Unit 1 South Wall 740.5 1-26-687 f
South Wall 706 1-26-686 f.
Auxiliary Building 759 1-26-669 749 2-26-664 749 1-26-664 734 2-26-670 734 0-26-684 734 1-26-670 734 0-26-682 734 1-26-671 Siamese Outlet 734 1-26-672 734 1-26-665 714 0-26-660 714 1-26-666 714 0-26-677 706 0-26-658 690 0-26-690 690 0-26-661 690 1-26-674 Siamese Outlet 690 1-26-675 690 1-26-667 669 1-26-668 669 0-26-662 e
669 0-26-680 653 0-26-663 653 0-26-691 SEQUOYAH - UNIT 1 3/4 7-39 Amendment No. 13
TABLE 3.7-5 (Continued)
FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #
g.
CCW Intake Pumping Station 690 0-26-866 690 0-26-867 690 0-26-868 690 0-26-869 690 0-26-870 h.
ERCW Pumping Station 688 0-26-927 688 0-26-926 688 0-26-930 704 0-26-931 704 0-26-925 704 0-26-928 720 0-26-929 720 0-26-924 720 0-26-932 1
SEQUOYAH - UNIT 1 3/4 7-40 Amendment No. 13 l
t
TABLE 4.12-1 (Continued)
TABLE NOTATION
/
\\s b.
The LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/1.
If levels greater than 15 pCi/1 are identified in surface water samples downstream from the plant, or in the event of an unantici-pated release of I-131, drinking water samples will be analyzed.at a LLD of 1.0 pCi/1 for I-131.
c.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
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SEQUOYAH - UNIT 1 3/4 12-9
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest. garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gar. dens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)
APPLICABILITY:
At all times.
ACTION:
With a land use census identifying a location (s) which yields a a.
calculated dose or dose commitment greater than the maximum values currently being calculated in Specification 4.11.2.3.1, in lieu of any other report required by Specification 6.9.1., prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s).
b.
With'a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than the highest calculated dose or dose commit-ment at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location.
The new location shall be added to the radiological environmental monitoring program within 30 days, if the owne'r consents.
The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:
1.
Within a 2.-mile radius from the plant or within the 15-mrem / year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.
2.
Within a 5-mile radius from tha plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone-survey, aeriai survey, or information from local agricultural authorities or other reliable sources.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
SEQUOYAH - UNIT 1 3/4 12-10 Amendment No. 13
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i SEQUOYAH - UNIT 1 5-3 t
a a
- 5. 3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1766 grams uranium.
The initial core loading shall have a maximura enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4,0 weight percent U-235.
CONTROL ROD ASSEMBLIES
- 5. 3. 2 The reactor core shall contain 53 full length and ne part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM e
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 of a.
g the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, 1
b.
For a pressure of 2485 psig, and For a temperature of 650 F, except for the pressurizer which is c.
680 F.
VOLUME 5.4.2 The total water.and steam volume of the reactor coolant system is 12,612 + 100 cubic feet at a nominal T of 525"F.
)
t
- 5. 5 METEOROLOGICAL TOWER LOCATION
[
5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SEQUOYAH - UNIT I 5-4 Amendment No. 13 i
i
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL
- 5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than 0.95 when flooded with unborated eff water, which includes a conservative allowance of 1.42% delta k/k for uncertainties.*
b.
A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage ranks.
j CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21.0 center-to center distance between new fuel assemblies such that k will n t exceed 0.98 when fuel having a maximum enrichment of 4.5 eff weight percent U-235 is in place and optimum achievable moderation is assumed.
DRAINAGE 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained witn a storage capacity limited to no more than 1386 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT t
5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
i t
l l
r
- For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.
SEQUOYAH - UNIT 1 5-5 Amendment No. 13
ADMINISTRATIVE CONTROLS c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Director, Nuclear Power Division within 14 days of the violation.
6.8 PROCEDURES & PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Plant Physical Security Plan implementation.
e.
Site Radiological Emergency Plan implementation.
f.
Fire Protection Program implementation, g.
PROCESS CONTROL PROGRAM implementation.
h.
Quality Assurance Program for effluent monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
-The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PORC and approved by the Plant Superintendent within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained by the Radiological Hygiene Branch covering the activities below; a.
OFFSITE DOSE CALCULATIONAL MANUAL implementation.
SEQUOYAH - UNIT 1 6-15 Amendment No. 13
ADMINISTRATIVE CONTROLS b.
Quality Assurance Program and environmental monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977.
c.
Surveillance requirements and environmental monitoring requirements shown in Table 6.1-1.
6.8.5 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the charging system, safety injection system, residual heat removal system, chemical and volume control system, containment spray system, iodine cleanup system, and hydrogen recombiner system.
The program shall include the following:
(i) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentrations in vital areas under accident conditions.
This program shall include the following:
(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include:
(i) Identification of a sampling schedule for the critical variables and control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, (iii)
Identification of process sampling points, SEQUOYAH - UNIT 1 6-15a Amendment No.
13
s 4
TENNESSEE VALLEY AUTHORITY DOCKET tiO. 50-328 SE000YAH HUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment Ho. 4 License Ho. DPR-79 1.
The Huclear Regulatory Commission (the Connission) having found that:
A.
The applications for amendnent to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated Ceconber 10, 1981 (two letters), March 1, March 9, and April 7,1982, comply with the stand-ards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Concission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the license, as anended, the provisions of the Act, and the rules and regulations of the Con-mission; C.
There is reasonable assurance (i) that the activities authorized by this amendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cocpliance with the Connission's regulations; D.
The issuance of this amendment will not be ininical to the comnon defense and security or to the health and safety of the public; and E.
The issuance of this anendnont is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby anended by page changes to the Appendix A Technical Specifications as indicated in the attachments to this license amendnent and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby anended to read es follows:
I
- 2) Technical Specifications The Technical Specifications contained in Appendix A, as revised j
through Arendment do. 4, are hereby incorporated into the license.
omer >
sunsuie) om) une ronu sia cio-ec) uncu em OFFIClAL RECORD COPY usom,u_m
2 The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of its date of issuance.
FOR THE IUCLEAR REGULATORY C0fti!SS10fl r?
L Elinor G. Adensan, Chief Licensing Branch tio. 4 Division of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance: May 4, 1982 LA:DL:gB..f4......D g.ta..... 0 ELD............
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l' ATTACHL'ErlT TO LICENSE A"El:DMENT !!0. 4 FACILITY OPERATIMG LICENSE H0. OPP.-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pancs. The revised pages are identified by Anendrent number and contain vertical lines indicating the area of change. The corresponding over-leaf paqes are also provided to naintain docu.9ent completeness.
Overleaf Amended Pann Pane 2-R 2-7 3/4 3-76 3/4 3-75 3/4 3-81 3/4 3-R2 3/4 6-19 3/4 6-20 3/4 6-30 3/4 6-29 3/4 7-43 3/4 7-44 3/4 9-8 3/4 9-7 3/4 12 9 3/4 12-10 s-6 s-s 6-17 6-18 6-20 6-19 5-3 5-4 l
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TABLE 2.2-1 (Continued)
~
. REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS SE E
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 4
b 21.
Turbine Impulse Chamber Pressure -
< 10% Turbine Impulse
< 11% Turbine Impulse (P-13) Input to Low Power Reactor Trips Pressure Equivalent Pressure Equivalent
^'
Block P-7 i
22.
Power Range Neutron Flux - (P-8) Low 5 35% of RATED
$ 36% of RATED Reactor Coolant Loop Flow, and TliGMAL POWER THERMAL POWER R:: actor Trip i
23.
Power Range Neutron Flux - (P-10) -
2 10% of RATED 2 9% of RATED Enable block of Source, Intermediate, THERMAL POWER THERMAL POWER and Power Range (low setpoint) reactor Trips
]
24.
Reactor Trip P-4 Not Applicable Not Applicable 25.
Power Range Neutron Flux - (P-9) -
5 50% of RATED 5 51% of RATED Blocks Reactor Trip for Turbine THERMAL POWER THERMAL POWER Trip Below 50% Rated Power NOTATION I
2 (1
- 2 )[T(
)-T'] + K I
) - I (O )I 5
I NOTE 1:
Overtemperature AT (
) 5 AT, {Kj -K 3
1 1+15 1+1 I*I 3
3 4
s S
1 g
where.
- Lag compensator on measured AT j.
g 1
a j
= Time constants utilized in the lag compensator for AT '1 = 2 secs.
T 3
AT,
= Indicated AT at RATED THERMAL POWER 3
K
$ 1.14 j
K
= 0.009 2
TABLE 4.3-8 (Continued)
TABLE NOTATION During liquid additions to the tank.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Downscale failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that part.icipate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
SEQUOYAH - UNIT 2 3/4 3-75 Amendment No. 4
TABLE 4.3-9 (Continued)
TABLE NOTATION At all times.
During waste gas disposal system operation.
During shield building exhaust system operation.
- During waste gas releases.
(1) The CHANNEL FUNCTIONAL TEST chall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
l (4) The CHANNEL CALIBRATION shall include the use of standard gas samples j
containing a nominal:
1.
One volume percent hydrogen, balance nitrogen, and 2.
Four volume percent hydrogen, balance nitrogen.
l i
l (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent oxygen, balance nitrogen, and 2.
Four volume percent oxygen, balance nitrogen.
SEQUOYAH - UNIT 2 3/4 3-82 Amendment No. 4 l
TABLE 3.6-2 mjj CONTAINMENT ISOLATION VALVES s
x e
VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)
C5 A.
PHASE "A" ISOLATION
-d 1.
FCV-1-7 SG Blow Dn 10 2.
FCV-1-14 SG Blow Dn 10 3.
FCV-1-25 SG Blow Dn 10 4.
FCV-1-32 SG Blow Dn 10 5.
FCV-1-181 SG Blow Dn 15 6.
FCV-1-182 SG Blow Dn 15 7.
FCV-1-183 SG Blow Dn 15 8.
FCV-1-184 SG Blow Dn 15 9.
FCV-31C-222 CW-Inst Room Clrs 10 10.
FCV-31C-223 CW-Inst Room Clrs 10 11.
FCV-31C-224 CW-Inst Room Clrs 10 12.
FCV-31C-225 CW-Inst
- Room Clrs 10 R
13.
FCV-31C-229 CW-Inst Room Clrs 10 14.
FCV-31C-230 CW-Inst Room Clrs 10 T
15.
FCV-31C-231 CW-Inst Room Clrs 10 U$
16.
FCV-31C-232 CW-Inst Room Clrs 10 17.
FCV-43-22 Sample RC Outlet Hdrs 10 18.
FCV-43-23 Sample RC Outlet Hdrs 10 19.
FCV-43-55 SG Blow Dn Sa.aple Line 10 20.
FCV-43-58 SG Blow Dn Sample Line 10 21.
FCV-43-61 SG Blow Dn Sample Line 10 22.
FCV-43-64 SG Blow Dn Sample Line 10 23.
FCV-61-96 Gylcol Inlet to Floor Cooler 30 E
24.
FCV-61-97 Gylcol Inlet to Floor Cooler 30 25.
FCV-61-110 Gylcol Outlet to Floor Cooler 30 E
26.
FCV-61-122 Gylcol Outlet tn Floor Cooler 30 9
27.
FCV-61-191 Ice Condenser - Gylcol In 30 28.
FCV-61-192 Ice Condenser - Gylcol In 30 5
29.
FCV-61-193 Ice Condenser - Gylcol Out 30 30.
FCV-61-194 Ice Condenser - Gylcol Out 30 31.
FCV-62-61 RCP Seals 10
TABLE 3.6-2 (Continued) y, CONTAINMENT ISOLATION VALVES 5!
E i
VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) 9
..o 5
A.
PHASE "A" ISOLATION (Cont.)
32.
FCV-62-63 RCP Seals 10 33.
FCV-62-72 Letdown Line 10 34.
FCV-62-73 Letdown'Line 10 35.
FCV-62-74 Letdown.Line 10 36.
FCV-62-77 Letdown Line 10 37.
FCV-63-23 Accum to Hold Up Tank 10 38.
FCV-63-64 WDS N to Accum 10 39.
FCV-63-71 Accum to Hold Up Tank 10 40.
FCV-63-84 Accum to Hold Up Tank 10 41.
FCV-68-305 WDS N to PRT 10 42.
FCV-68-307 PRTt$GasAnalyzer 10 43.
FCV-68-308 PRT to Gas Analyzer 10 g
's 44.
FCV-70-85 CCS from Excess Lt Dn Hx 10 45.
FCV-70-143 CCS to Excess Lt Dn Hx 60 i
46.
FCV-77-9 RCDT Pump Disch 10 47.
FCV-77-10 RCDT Pump Disch 10 48.
FCV-77-16 RCDT to Gas Analyzer 10 49.
FCV-77-17 RCDT to Gas Analyzer 10 50.
FCV-77-18 RCDT and PRT to V H 10 51.
FCV-77-19 RCDT and PRT to V H 10 52.
FCV-77-20 N to RCDT 10 53.
FCV-77-127 F$oorSumpPumpDisch 10 54.
FCV-77-128 Floor Sump Pump Disch 10
[
55.
FCV-81-12 Primary Water Makeup 10 s
56.
FCV-87-7 UHI Test Line 10 E
57.
FCV-87-8 UHI Test Line 10 58.
FCV-87-9 UHI Test Line 10 59.
FCV-87-10 UHI Test Line 10 5
60.
FCV-87-11 UHI Test Line 10 61.
FCV-26-240 Fire Protection Isol.
20 62.
FCV-26-243 fire Protection Isol.
20
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 indication not available in the main control room, determine the ice bed temperature at the local ice condenser temperature monitoring panel every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the ice bed temperature monitoring system inoperable, and a.
unable to determine ice bed temperature at the local panel, 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 unable to determine the ice bed temperatures by alternate means with the ice condenser cooling system not satisfying the. minimum components OPER-ABILITY requirements of a.3 above, POWER OPERATION 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; other-wise, 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 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 2 3/4 6-29 Amendment No. 4
PLANT SYSTEMS ACTION:
(Continued) c)
In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
l SURVEILLANCE REQUIREMENTS I
4.7.11.1 The fire suppression water system shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by starting each a.
electric motor driven pump and operating it for at least 15 minutes on recirculation flow.
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.
l
- c.
At least once per 6 months by performance of a system flush, d.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
At least once per 18 months by performing a system functional test e.
which includes simulated automatic actuation of the system throughout its operating sequence, and:
1.
Verifying that each automatic valve in the flow path actuates to its correct position, 2.
Veri.fying that each pump develops at least 1174 gpm at a system head of 312 feet, 3.
Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 4.
Verifying that the No. 1 fire pump starts to maintain the fire suppression water system pressure greater than or equal to 125 psig, and that the No. 2 fire pump starts automatics'ly within 10 2 seconds if the fire suppression water systrn is not maintained at greater than or equal to 125 psig by the No. I pump.
f.
At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
- Note:
These flushes should coincide with the chlorination of the raw service
.and fire suppression water system.
These flushes should be run, one between April 1 and June 30, and the other between September 1.and November 15.
Within the prescribed spring and fall test period, deviation from the six-month performance frequency is authorized.
SEQUOYAH - UNIT 2 3/4 7-44 Amendment No. 4
REFUELING OPERA ~ f 3/4.9.6 MANIPULATOC CRANE LIMITING anDITION FOR OPERATION 3.9.6 The manipulator crane and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be OPERABLE with:
The manipulator crane used for movement of fuel assemblies having:
a.
1.
A minimum capacity of 2750 pounds, and 2.
An overload cut off limit less than or equal to 2700 pounds, b.
The auxiliary hoist used for latching and unlatching drive rods having:
1.
A minimum capacity of 610 pounds, and 2.
A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.
APPLICABILITY:
During movement of drive rods or fuel assemblies within the reactor pressure vessel.
ACTION:
With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of drive rods and fuel assemblies within the reactor pressure vessel.
The provisions of S'pecification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.6.1 Each malipulator crane used for movement of fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 2750 pounds and demonstrating an automatic electrical; load cut off when the crane load exceeds 2700 pounds, and a mechanical load cutoff when the crane load exceeds 2800 pounds.
4.9.6.2 Each auxiliary hoist and associated load indicator used for movement of drive rods within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 610 pounds, SEQUOYAH - UNIT 2 3/4 9-7 Amendment No. 4
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteoro-logical sectors within a distance of five miles.
(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteoro-logical sectors within a distance of three miles.)
APPLICABILITY:
At all times.
ACTION:
With a land use census identifying a location (s) which yields a calcu-a.
lated dose or dose commitment greater than the msximum value currently being calculated in Specification 4.11.2.3.1, in lieu of any other report required by Specification 6.9.1., prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specific-ation 6.9.2, a Special Report which identifies the new location (s).
b.
With a land use census identifying a location (s) which yields a calcu-lated dose or dose commitment (via the same exposure pathway) 20 percent greater than the highest calculated dose or dose commitment at a location from which samples are currently being obtained in accordance with Speci-fication 3.12.1, in lieu of any other report required by Specifi-cation 6.9.1, prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location.
The new location shall be added to.the radiological environmental monitoring program within 30 days, if the owner consents.
The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:
1.
Within a 2-mile radius from the plant or within the 15-mrem / year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.
2.
With a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, serial Survey, or information from local agricultural authorities or other reliable sources.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
SEQUOYAH - UNIT 2 3/4 12-10 Amendment No. 4
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SEQUOYAH - UNIT 2 5-3
_~,
[
t DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4.
Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1766 grams uranium.
The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.0 weight percent U-235.
n CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.
The full length control rod assemblies shall contain c
a nominal 142 inches of absorber material.
The nominal values of absorber caterial shall be 80 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
k.
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650 F, except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,612 + 100 cubic feet at a nominal T f 525 F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 4
5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
(
SEQUOYAH - UNIT 2 5-4 Amendment No. 4
e DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than 0.95 when flooded with unborated a.
water, which includes a conservative allowance of 1.42% delta k/k for uncertainties.*
b.
A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage racks.
CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21.0 inch center-to-center distance between new fuel assemblies such that k will n t exceed 0.98 when fuel having a maximum enrichment of eff 4.5 weight percent U-235 is in place and optimum achievable moderation is assumed.
DRAINAGE 5.6.2 The spcat fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.
i l
CAPACITY l
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1386 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT
- 5. 7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limit; of Table 5.7-1.
- For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.
SEQUOYAH - UNIT 2 5-5 Amendment No. 4
ADMINISTRATIVE CONTROLS c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Director, Nuclear Power Division within 14 days of the violation.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Plant Physical Security Plan implementation.
e.
Site Radiological Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
Quality Assurance Program for effluent monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PORC and approved by the Plant Superintendent within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained by the Radiological Hygiene Branch covering the activities below:
a.
OFFSITE DOSE CALCULATIONAL MANUAL implementation.
SEQUOYAH - UNIT 2 6-18 Amendment No. 4
ADMINISTRATIVE CONTROLS b.
Quality Assurance Program and environmental monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977.
2 c.
Surveillance requirements and environmental monitoring requirements shown in Table 6.1-1.
6.8.5 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a i
serious transient or accident to as low as practical levels.
The systems include the safety injection system, residual heat removal system, chemical and volume control system, containment spray system, and RCS sampling system. The program shall include the following:
(i) Preventive maintenance and periodic visual inspection requirements, and (ii)
Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentrations in vital areas under accident conditions.
This program shall include the following:
1 (i) Training of personnel, (ii) Procedures for monitoring, and (iii)
Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary wate chemistry to inhibit steam generator tube degradation.
This pr gaim shall include:
(i)
Identification of a sampling schedule for the critical variables and control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, (iii)
Identification of process sampling points, SEQUOYAH - UNIT 2 6-19 Amendment No. 4
.__.