ML20006D621
| ML20006D621 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/02/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006D623 | List: |
| References | |
| NUDOCS 9002140133 | |
| Download: ML20006D621 (14) | |
Text
{{#Wiki_filter:(* A $ msc / so, UNITED STATES 8; 'i NUCLEAR REGULATORY COMMISSION l ,,o 1: '{- -.I WASHINGTON,0. C,20556 l t t %, v,/ Y1RGINT A ELECTRIC AND POWER COMPANY OLD CCHINION ELECTRIC COOPERATIVE j DOCKET NO 50-338 FORTH ANNA POWER STATION. UNIT NO.1 l AMENDMENT TO FACILITY OPERAT1HG LICENSE [ i Arendment No. 125 License No. NPF-4 1. The Nuclear Regulatory Comission (the Commission) has found that: A. The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 12, 1969, complies with the standards and requirements of the Atomic Energy Act of 1954, as ar, ended (the i 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 Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conoucted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; t D. The issuance of this anendment will not be inimical to the comon l defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirenants have been satisfied. f,f)hki f L .P 1
t j 1.s. : 1 l 2. Accordingly, the license is amended by changes to the Technical Speci-fications as indicateo in the attachment to this licehse asendment, and paragraph 2.D.(2) of facility Oper6 ting License No. NPF.4 is hereby an. ended to read as follows: i p (2) Technical Specifications l l The Technical Specifications contained in Appendices A and B, i as revised through Ariendment No.125 -. are hereby incorporated t t in the license. The licensee shall operate the facility in b accordar.ce with the Technical Specifications 3. This license anendnent is effective as of the date of issuance and shall be implemented within 30 days, FOR THE NUCLEAR RECULATORY COW.lSS10N ( 6:. h v-i H bert N. Berkow. Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachnent: Char.tes to the Technical Specifications Date of Issuance: February 2,1990 [ f b j 4
m A + ATTACHMENT TO LICENSE AMENDMENT NO.125 i TO FACILITY OPERATil;G LICENSE i;0. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Apptndix "A" Technical Specifications with tho enclosed pages as indicated. The revised pages are identified by amendment nunt>er and cos,13in vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completene ss. ) Page la 1-5 l 1-6 t i i a b v
e 9 .c INotx } i DETINITIONS i i SECTION PAGE l c 1.0 DETINITIONF Action............................................................. 1-1 ' I Axial Flux Difference............................................. 1-1 I Channel Calibration................................................ 1-1 1 t t Channel Check...................................................... 1-1 h Channel Tunctional Test............................................ 1-1 Cortainment, Integrity............................................. 1-1 [ Controlled Leakage................................................. 1-2 Core Alteration.................................................... 1-2 - i Dose Equivalent 1-131.............................................. 1-2 I-Average Disintegration Energy.................................... 1-2 f Engineered Safety Teature Response Time..................... 1-3 ~ Frequency Notation................................................. 1-3 i Gaseous Radwaste Treatment System.................................. 1-3 Identified Leakage................................................. 1-3 Member (s) of the Public............................................ 1-3 Offsite Dose Calculation Manual (0DCM)............................. 1-4 l Operable - Operability............................................. 1-4 Operational Mode - Mode............................................ 1-4 t Physics Tests...................................................... 1-4 P r e s s u r e B ou n da ry Le a ka g e.......................................... 1-4 Process Control Pregram (PCP)...................................... 1-4 t Purge-Purging...................................................... 1-4 Quadrant Power Tilt Eatio.......................................... 1-5 . NORTH ANNA - UNIT-1 I Amendment No. 46 t -t
-.t s. \\_ ~ IND([(Cont'd) l
- i-SECTION PAGE-1.0 DEFINITIONS (Continued)
R a t e d T h e rm a l Po w e r...........................................,.. 1 5 Reactor Trip System Response Time................................ 1-5 R e po r t a bl e E v e n t................................................. 1 - 5 t Shutdown Margin.................................................. 1-5 i S i t e B o u n d a ry.................................................... 1 5 S l a v e R el a y T e s t................................................. 1 - 5 Sol i d i f i c a t i o n................................................... 1 - 5 S o u rc e C h e c k..................................................... 1 - 5 Staggered Text Basis............................................. 1-6 T h e rm a l P o w e r...................................................... 1 - 6 J U n i d e n t i f i e d L e a k a g e.............................................. 1 - 6 U n r e s t r i c t e d A r e a.................................................. 1 - 6 i' Ventilation Exhaust Treatment System............................. 1-6 Venting...............................-..................... ...... 1-6 i L 1 6 NORTH ANNA - UNIT 1 la Amendnent No. #S.6),125 j [ h.
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',1. 0 DEFIN!?!ONS (Con %inued) QUADRANT POWER TILT RATIO 1.23 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper ex-core detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the taximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average. RATED THERMAL POWER 1.24 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2893 MWt. REACTOR TRIP SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage. , REPORTABLE EVENT 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. SHUTDOWN MARGIN 1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY 1.28 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by.the licensee. SLAVE RELAY TEST 1,29 A SLAVE REL AY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable
- actuation devices.
SOLIDIFICATION ,1.30 SOLIDIFICATION shall be the conversion of wet wastes into a l l solid form that meets shipping and burial ground requirements. SOMCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel l response when the channel sensor is exposed to radiation. This applies to installed radiation monitoring systems. NORTH ANNA - UNIT 1 1-5 Amendment No.16,$8,63,f f,125
s L 4 L 1.0 DETINITIONS (Centinued) STAGGERED TEST BASIS 1.32 A STAGGERID TEST BASIS shall consist of: a. A test schedule for a systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, b. The testing of one systes, subsystem, train or other designated component at the beginning of each subinterval. THER*.AL POVER 1.33 THERMAL POVER shall be the total reactor core heat transfer rate to the reactor coolant. UNIDENTIFIED LEAY. AGE 1.34 UNIDENTITIED LEAKAGE shall be all leakage which is not IDENTITIED LEAKAGE or CONTROLLED LEAKAGE. UNRESTRICTED AREA -1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY l where access is not controlled by the licensee for purposes of protection of individuals f rom exposure to radiation and radioactive materials or any area within the SITE EOUNDARY used for residential quarters or for industrial, commercial institutional, rand /or tocreational purposes. VENTILATION EXRAUST TRIATMENT SYSTEM' l-it .c' l.36 A VENTILATION EXHAUST TREATMENT SYSTDi is, the system. designed and n@ installed to reduce gaseous radiciodine or radioactive material in particulate tr, form in effluents by passing ventilation or vent exhaust gases through i &.s . charcoal adsorbers and/or BEPA filters for the; purpose of removing iodines or e' particulates from the - gaseous exhaust - streaa prior to. the release to. the e. environment (such a system is not censidered to have any effect on noble gas y effluents). Engineered Safety Teature (EST) atmospheriev elaanup. systems are P" not considered to be VENTILATION. EXHAUST TREA F NT SYSTEM components. ?> VENTING. l h 1.37 VENTING is the controlled process of discharging air or gas f rom a WY confinement to maintain temperature, pressure, humidity, concentration or n other. operating condition, in such a manner that replacement air or gas is net-provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. Ih NORT1! ANNA:- UNIT 1 1-6 Amendment No.16, 4 g
- 125 i
i
l [ 'o,, UNITED STATES h. NUCLE AR REGULATORY COMMISSION .,1 g w AssiNoton. o. c. 20555 %,,.w..,..,/ VIRGINI A ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH AtlNA POWER STATION, UNIT NO. 2 AMENDMENT _TO FACILITY OPERATING LICENSE Amenenent No,109 License No. NPF-7 J 1. The Nuclear Regulatory Cotrmission (the Commission) has found that: A. The application for amendment by Virginia Electric and Power Company, conplies with the standards et al.,~ (the licensee) dated July 12,1989,f 1954, as amended (the and requireterts of the Atomic Energy Act o Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1; 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 ameneent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuana of this anendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirenants have been satisfied. 1
~ h,Y ( l y ys v -} p p 6 3 P,. - 1 8' i . 2. Accordingly, the license is amended-by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, anc paragraph 2.C.(2) of facility Operating License No. hPF-7 is hereby amended to read as follows: (2)T Ttchnical Specificatiog The Technical Specifications contained in Ap)endices A and B, as revised through Anendment No.- 109, are 1ereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This li:ense amendment is effective as of the date of issuonce and shall be implemented within 30 days. FOR THE NUCLEAR REGULATORY CCWISSION ./ p ( L. (Av He ert N. Berkow, Director Project Directorate 11-2 I Division.of Reactor Projects,-- 1/II Office of Nuclear Reactor Regulation R
Attachment:
i: ' Changes to the Technical Specifications Date of Issuance: February 2, 1990 L i h f i; I j +'-f'- '4 m . l m
l 4
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[ ATTACHMENT T6 LICENSE AMENDMENT NO.109 l 10 FACILITY CPERATING LICENSE NO. NPF-7 DOCKET fl0. 50-339 P.ep1' ace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by anendment nunter end contain vertical lines. indicating the area of change. The corresponding overleaf pages are also provided to r,aintain docunent completeness. Page la 1-5 1-6 i; t i, l[ v s' i l '. 3 s p a
. n .M hL 9 t t INDEK i 1 t' . ^ c j DEFINI7 IONS f SECTION-PAGE l i l 1.0 DEFINITIONS' 4 - Action............................................................. 1-1 c' Axial Flux Difference.............................................- 1-1 I 4 c Channel Ca11bration................................................ 1-1 e Channel Check...................................................... 1-1 t Channel Functional Test............................................ 1-1 l' Containment Intergrity.............................................- 1-l' - Controlled Leakage................................................, 1-2 Core Alteration'.................................................... 1-2 i' Dose Equivalent I-131.............................................. 1-2 t E-Average D1'sintegration Energy.................................... 1-2 e 'l-3 Engineered Safety Feature Response Time............................ ' Frequency: Notation................................................. 1-3 I . Gaseous Radwaste Treatment System................................... 1-3 Identified Leakege.................................................. 1-3. E Member (s) of the Public.e 'l-3 ' I Offsite Dose Calculation Manual (0DCM)............................. 1-4 . Operable - Operability............................................. 'l-4 'Operatioce: Mode - Mode............................................ 4 Physics-Tests...........................:.......................... 1-4 P r e s su re - Bound ry Le aka g e........................................... 1-4 Process Control Program (PCP)...................................... 1-4 .l4
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. Purge-Purging...................................................... 1-4 [ ~ Quadrant-Power Tilt Ratio.......................................... 1-5 NORTH ANNA-- UNIT 2 1 Amendment No. 31 i 'f 6
m. ..y ~ INDEX'(Cont'd) SECTION PAGE-1.0 DEFINITIONS (Continued) R a t ed T h e rm a l Po w e r.............................................. 1 Reactor Trip System Response Time................................ 1-5 R e po r t a bl e E v e n t................................................. 1 Shutdown Margin.................................................. 1-5 S i t e B o u n d a ry.................................................... 1 - 5. Sl a v e - R e l a y Te s t................................................. 1 - 5 Solidification...................................................1-5 2 SourceCheck.....................................................1-5 S ta gge red Te x t B a s i s............................................-. 1 - 6. Thermal Power.................................................... 1 U n i d e n t i f i e d L e a k a g e................... -........................... 1. U n r e s t r i c t e d A r e a................................................... 1 - 6 Ventila tion Exhaust Trea tment System....-.............-............. 1-6. 2 V e n t i n g................................................................. 1 - 6 ' ri A F .]. D t" ' NORTH ANNA' UNIT 2 la Amendment No. 37,$7,109-m i p .i i 1 .L
l 15 0 DEFINITIONS (Continued) QUADRANT POWER TILT RATIO l.23 - QUADRANT. POWER TILT RATIO shall be the ratio of the maximum upper ex-t core dctector calibrated output to the average of ~the upper excore detector ' calibrated outputs, or the' ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.- RATED THERMAL POWER 1.24 ' RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor' coolant of 2893 MWt. REACTOR TRIP SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be'the time interval from when the monitored: parameter exceeds its trip setpoint at the channel sensor until loss.of stationary gripper coil ~ voltage. REPORTABLE EVENT 1.26 A' REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.. SHUTDOWN MARGIN 1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be suberitical from its present condition assuming all full length rod cluster assemblies (shutdown and control)'are fully. inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be 'ully withdrawn. r SITE BOUNDARY. t 1.28 _ The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee. SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERASILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of_ associated testable actuation devices. i SOLIDIFICATION < l.30 SOLIDIFICATION shall be the conversion of wet wastes into a l-h solid form that meets shipping and burial ground requirement's. SOURCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel l response when the channel sensor is exposed to radiation. This applies to installed radiation monitoring systems. NORTH ANNA - UNIT 2 1-5 Amendment No. 37,57.77. 109
W; =-.,, L DEFINITIONS (Continued) 1.0 STAGGEFID TEST BASIS I 1.32 A' STAGGERED TEST BASIS shall consist of: a.--A test schedule for n systems, subsystems, trains or other designated components cbtained by dividing the specified . test interval into n equal subintervals. b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval. THERMAL POWER ( 1.3 3' THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. UNIDENTIFIED LEAKAGE l 1.34 UNIDENTIFIED. LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE. UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA, shall be any area at or beyond the SITE BOUNDARY. where access is not controlled by the licensee.for purposes of protection of ;, - individuals f rom ' exposure' to radiation and radioactive materials or: any area 4 within the : SITE. BOUNDARY msed for residential quarters,or, f oreindustrial - commercial. institutional ~,'and/or recreational purposes'.. u. VENTILATION EXRAUST TREATMENT SYSTEM -{ l.36 A VENTILATION 'EXEAUST TREATMENT SYSTEM is the system ~ designed and- "" C installed to reduce gaseous radiciodine or. radioactive 3 material in particulate tia form in effluents by passing ventilation or vent exhaust gases through P,t charcoal adsorbers and/or-HEPA: filters for the purpose 'of removing iodines or, Q cr- ' particulates. f rom the gaseous exhaust stream'. prior-to. the release ; to ithe W/ ^ ' environment (such-a system is not considered to have: any. effect' on. noble gas tt. N. effluents). Engineered Safety Feature (EST)- atmospheric cleanup. systems L are : .i ke' not.conside ed to be VENTILATION EXHAUST TREATMENT' SYSTEM' components. s - VENTING. ? f'. Dis 1.37-VENTING is the controlled process - of discharging air: or gas f rom a, e .QC < confinement to maintain temperature, pressure, humidity - concentration o r-other operating condition, in such a-manner that replacement-air.or gas-is not y provided - or required during VENTING. Vent, used, in system names, does not. 4 imply a VENTING process. Ta?> NORTH MNA:- UNIT 2 1-6 Amendment No.J y,109; .}}