ML20236J233
| ML20236J233 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/30/1987 |
| From: | Zwolinski J NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20236J236 | List: |
| References | |
| NUDOCS 8711050219 | |
| Download: ML20236J233 (18) | |
Text
{{#Wiki_filter:- _ - _ _ (pmagjo UNITED STATES - g NUCLEAR REGULATORY COMMISSION ,[ .g O E WASHING TON, D. C. 20555 g TENNESSEE VALLEY AUTHORITY a 00CKET NO. 50-327. SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE I .l Amendment No. 62 i License No. DPR-77. l 1. The Nuclear Regulatory Comission (the Comission) has found that: 'A. The application for amendment by Tennessee Valley Authority (the licensee) dated January 21, 1987, as clarified by a letter dated 1 March 25, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The. facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authori7ed 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon l defense and security or to the health and safety of the public; and { 4 E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comissions regulations and all applicable requirements have been satisfied. l l 8711050219 871030 ' DR ADOCK 050 7 1
i -2. l 2. Accordingly, the. license is amended by changes to the Technical Specifications as. indicated in the attachment to this ifcense amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-77 is hereby i! amended to read as.follows: j ) .(2). Technical Specifications-The Technical Specifications contained in Appendices A and B, as - j revised through' Amendment No. 62, are hereby. incorporated in the W 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. FOR THE' NUCLEAR REGULATCmY COMMISSION John A. Zwolinski, Assistant' Director foH Projects TVA Projects Division Office of Special Projects
Attachment:
Changes.to the Technical Specifications i Date of Issuance: October 30, 1987 O ___w
w ,}. ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. DPR-77 i e DOCKET NO. 50-327 Revise the Appendix A Technical.Specifica'tions by removing.the pages identified below and. inserting the enclosed pages. The revised pages 'l are identified by.the captioned amendment number and contain marginal lines. indicating the area of change. Overleaf pages* are provided to maintain document completeness. l . REMOVE INSERT. .q V V 0 VI VI*. f 3/4 3-53 3/4 3-53* 3/4'3-54 '3/4 3-54 B 3/4 3-3 'B 3/4 3-3 B 3/4 3-4 B 3/4 3-4* l i i b l 1 l l
it .-p:. INDEX i. q LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENTS 1 SECTION PAGE 3/4.2 POWER D' DISTRIBUTION LIMITS 3/4.2.1 ' Axial Flux Difference..................................... 3/4 2-1 1
- 3/4.2.2.' Heat. Flux Hot Channel Factor.........,....................
3/4 2 3/4.2.3-RCS'Flowrate and R........................................ 3/4 2-10 -{ l 3/4.2.4 Quadrant Power. Tilt Ratio................................. 3/4 2-15 F3/4.2.51 :DNB Parameters............................................ 3/4 2-18 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP ' SYSTEM INSTRUMENTATION....................... 3/4 3-1 ' 3/4. 3. 2.- ENGINEERED SAFETY FEATURE ACTUATION SYSTEM f INSTRUMENTATION......................................... 3/4 3-14 . 3/4'. 3. 3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....................... 3/4 3-39 Movable Incore Detectors.................................. 3/4 3-43 1 1 Seismic Instrumentation................................... 3/4 3-44 Meteorological Instrumentation............................ 3/4 3-47 1 Remote Shutdown Instrumentation.......................... 3/4 3-50 l Chlorine Detection Systems (Deleted) 3/4 3-54 Accident Monitoring Instrumentation....................... 3/4 3-55 Fire Detection Instrumentation............................ 3/4 3-58 Radioactive Liquid Effluent Monitoring Instrumentation.... 3/4 3-69 \\ Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-74 l SEQUOYAH - UNIT 1 V Amendment No.62 j l 1 ___ a
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM ( 3/4.4.1 REACTOR C0OLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration............................... 3/4 4-1 \\ + Hot-Standby............................................... 3/4 4-la Shutdown.................................................. 3/4 4-2 3/4.4.2 SAFETY VALVES - SHUTD0WN.................................. 3/4 4-3 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING Safety Valves - Operating................................. 3/4 4-4 Relief Valves - Operating................................. 3/4 4-4a 3/4.4.4 PRESSURIZER............................................... 3/4 4-5 3/4.4.5 STEAM GENERATORS.......................................... 3/4 4-6 q 3/4.4.6 REACTOR C0OLANT SYSTEM LEAKAGE Leakage Detection Systems................ 3/4 4-13 l Operational Leakage......................... 3/4 4-14 3/4.4.7 CHEMISTRY................................................. 3/4 4-16 3/4.4.8 SPECIFIC ACTIVITY......................................... 3/4 4-19 3/4.4.9 PRESSURE / TEMPERATURE LIMITS ) Reactor Coolant System.................................... 3/4 4-23 Pressurizer................... 3/4 4-26 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components..................... 3/4 4-27 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS Cold leg Injection Accumulators. 3/4 5-1 3/4 5-3 Upper Head Injection Accumulators......................... i SEQUOYAH - UNIT 1 VI
N - O -LI ET A. NA NR R N R R R R R R R R R R R AB HI CL A - C NO I TA T NE L MS EK UT NC RN NE M M M M M M M M M M M M M TE AH SM HC NE C IR 6 I GU 3 NQ IE 4 RR O E TE L IC B NN A OA s T ML e L h NI c WE t i OV DR w TU S US H t S g i e m E L i T L O t M o n e E n H o r R o i u i t e s t i t s a e s a e c r o R r x i u P P u d t 'e w l n a r d o k F I r u o l n e s l R F a r r p e s e T e a e m r e v l r r e k e u r e o e f u l a T s l P L r t e s c e s e t a i s u r t e v r r n e w l e N B n r e o o o r d e r a P L t t C e u e R P e p l a a t t e g i o r r r r h a a F r t n r o e e e e t R r e n a T C z z n n g e y z e R i i e e n w p r i m r r r r G G e o m a r n T e o o u u L l e i u i N c t t s s m m F T l s a E r c c s s a a l i s t M u a a e e e e l R R x e n U o e e r r t t u H H u r o R S R R P P S S F R R A P C T S 0 1 2 3 N I 1 2 3 4 5 6 7 8 9 1 1 1 1 >RR2a E. y >*
i 4 CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION This specification deleted. 3 f i l SEQUOYAH - UNIT 1 3/4 3-54 Amendment No. 62 s L________________
t / INSTRUMENTATION BASES-l E design basis for the facilitp to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. This instrumentation is consistent with'the. recommendations of Regulatory Guide 1.12, " Instrumentation i for Earthquakes," April 1974. ' 3/k.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological. instrumentation ensures that~ suf.ficient meteorological. data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials.to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public'and is consistent with the recommendations of Regulatory Guide 1.23, "0nsite Meteorological Programs," February 1972. ~ 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION -The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50. 3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.- 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant' parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975. E SEQUOYAH - UNIT 1 B 3/4 3-3 A end ent o 2
INSTRUMENTATION BASES Sequoyah has four separate methods of determining safety valve position (i.e., open or closed). l i a. Acoustic flow monitors mounted on each safety valve line (one per valve). A flow indicating module in the main control room is calibrated to detect O failure of a valve to reclose. An alarm in the main control room will actuate when any valve is not fully closed. b. Temperature sensors downstream of each safety valve (one per valve). Tem-i perature indication and alarm are provided in the main control room. I c. Pressurizer relief tank temperature, pressure and level indication, and { alarm in main control room. d. Pressurizer pressure indication and alarm in the main control room. Although all the above position indicators for the pressurizer safety valves and the PORVs are acceptable as one of the channels, the acoustic monitors must be one of the two required operable chanels. In addition to the four methods i described above, the PORVs use an electromagnetic " reed"-switch to determine ] valve position. The stem mounted switches are no longer in use since the PORVs q were changed. s l 1 i l ) l I i l i i O i 1 SEQUOYAH - UNIT 1 8 3/4 3-4 Amendment No. 43 Revised 08/18/87
u;.[ ' 'o,, UNITED STATES NUCLEAR REGULATORY COMMISSION o WASHINGTON, D. C. 20555 r -g %...../ TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i Amendment No. 54 l License No. DPR-79 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Tennessee Valley Authority (the licensee) dated January 21, 1987, as clarified by a letter dated March 25, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (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 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 accordance with 10 CFR Part 51 l of the Comission's regulations and all applicable requirements have i J been satisfied. l 1 l 4 I - - - ~ ~. _ _ _
o R .2-L + l- ) ' ' 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 ~ l ' amended to. read as follows.: 'i o L -(2). Technical Specifications g l The Technical. Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the 4 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.
l: FOR THE NUCLEAR REGUL ORYrCOMMISSION \\5 John . Zwolinski, Assistant Director for Projects - TVA Projects Division Office of Special Projects-
Attachment:
Changes to the Technical Specifications Date of' Issuance: October 30, 1987 1
[ u 1 ATTACHMENT TO LICENSE AMENDMENT N0. 54 FACILITt OPERATING i.ICENSE N0. DPR-79 l 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. Overleaf pages* are provided to maintain document completeness. REMOVE INSERT V V VI-Vl* 3/4 3-55 3/4 3-55 3/4 3-56 3/4'3-56* B 3/4 3-3 B 3/4 3-3 l B 3/4 3-4 8 3/4 3-4* i ) l l 1 1 i i i
c \\ ( INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX 0IFFERENCE..................................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R.............................. 3/4 2-4 3/4.2.3 RCS FLOWRATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R............................................ 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO............................... 3/4 2-13 1 3/4.2.5 DNB PARAMETERS............................................ 3/4 2-16 3/4.3 INSTRUMENTATION k 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................... 3/4 3-1 i 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.......................... 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................... 3/4 3-40 Movable Incore Detectors................................ 3/4 3-44 Seismic Instrumentation................................... 3/4 3-45 Meteorological Instrumentation............................ 3/4 3-48 Remote Shutdown Instrumentation........................... 3/4 3-51 i Chlorine Detection Systems (Celeted) 3/4 3-55 Accident Monitoring Instrumentation........................ 3/4 3-56 Fire Detection Instrumentation........................... 3/4 3-59 Radioactive Liquid Effluent Monitoring Instrumentation.... 3/4 3-68 Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-76 SEQUOYAH - UNIT 2 V Amendment No.54
l Rh h i .i l' INDEX i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS y 'SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1' REACTGR COOLANT LOOPS AND COOLANT CIRCULATION i Startup and Power Operation............................... 3/4 4-1 1 Hot Standby............................................... 3/4 4-2 Hot' Shutdown.............................................. 3/4 4-3 Cold Shutdown............................................. 3/4.4-S y 3/4.4.2-SAFETY VALVES - SHUT 00WN.................................. 3/4 4-6 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING Safety Valves 0perating................................... 3/4 4-7 Relief Valves Operating.................................. 3/4 4-8 i 3/4.4.4 PRESSURIZER............................................... 3/4 4-9 .3/4.4.5 : STEAM GENERATORS.......................................... 3/4 4-10 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems................................. 3/4 4-17 Operational' Leakage....................................... 3/4 4-18 i 3/4.4.7-CHEMISTRY................................................. 3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY......................................... 3/4 4-24 3/4.4.9 PRESSURE / TEMPERATURE LIMITS i Reactor Coolant. System.................................... 3/4 4-28 l Pressurizer............................................... 3/4 4-32 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components..................... 3/4 4-33 SEQUOYAH - UNIT 2 VI
-,--v._ I \\ 't F - ~ it;'t s m j ' 1 m " INSTRUMENTATION' a, [ CHLORI'NE'DETECTIONSYSTEMS: ~ 4 .g n ~~ \\ O' LiMITINGCONDITION'FOR' OPERATION' ..a .i l t ,This specification deleted." l + 1 4 \\ .t.. r f s l -l 'l j .i. ( ) d 1
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.SEQUOYAH ,0 NIT 2 3/4 3-55 Amendment No. 54 3 Y .--L--____.__-.___.
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' INSTRUMENTATION ,l J ACCIDENT MONITORING INSTRUMENTATION L LLIMITING CONDITION FOR OPERATION i 3.3.3.7 The accident monitoring instrumentation channels shown is Table 3.3-10 ~ shall be OPERABLE. i APPLICA8ILITY: MODES 1, 2 and 3. . ACTION: With the number of OPERABLE accident monitoring instrumentation a. channels, except for the RCS subcooling margin monitor, less than the Required Number of Channels sh'own in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at-least HOT SHUTDOWN within the next 12 hours. i b. With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE. requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours or be in at least H0T SHUTDOWN within the next 12 hours. With the subcooling margin monitor inoperable for more than 48 hours, j c. the minimum shift crew (per Table 6.2-1) will be increased by one member who shall be dedicated to and capable of determining the l subcooling margin during an accident using existing instrumentation. l l l SURVEILLANCE REQUIREMENTS 4.3.4.7 Each accident monitoring instrumentation channel shall be demon-strated OPERABLE by performance of the CHANNEL Check and CHANNEL CALIBRATION operations at the frequencies shown in TABLE 4.3-7. SEQU0YAH - UNIT 2 3/4 3-56 Amendmant No. 32
i INSTRUMENTATION 1 BASES 1 3/4.3.3.3 SEISMIC INSTRUMENTATION (Continued) recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes," April 1974. 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to tne atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the pablic and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972. 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that suf-ficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50. 3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted. 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975. I I Sequoyah has four separate methods of determining safety valve position (i.e., open or closed). a. Acoustic flow monitors mounted on each safety valve line (one per valve). j A flow indicating module in the main control room is calibrated to detect failure of a valve to reclose. An alarm in the main control room will actuate when any valve is not fully closed. j i SEQUOYAH - UNIT 2 B 3/4 3-3 Amendment No. 35, 46,54 Revised 08/18/87
f INSTRUMENTATION BASES 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION (continued) b. Temperature sensors downstream of each safety valve (one per valve). Tem-perature indication and alarm are provided in the main control room, c. Pressurizer relief tank temperature, pressure and level indication, and = alarm in main control room, d. Pressurizer pressure indication and alarm in the main control room. Although all the above position indicators for the pressurizer safety valves and the PORVs are acceptable as one of the channels, the acoustic monitors must be one of the two required operable chanels. In addition to the four methods described above, the PORVs use an electromagnetic " reed"-switch to determine valve position. The stem mounted switches are no longer in use since the PORVs were changed. 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program. l In the event that a portion of the fire detection instrumentation is f inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. 3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materit s in liquid effuents during actual or potential releases of liquid effluentt,. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. 3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION i The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous ef fluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the 00CM to ensure that the alarm / trip will occur prior SEQUOYAH - UNIT 2 B 3/4 3-4 Amendment No. 25, 46 i '}}