Text

Amends 130 & 114 to Licenses NPF-4 & NPF-7,respectively, Relocating Radiological Effluent Tech Specs to ODCM or Process Control Program,As Appropriate
	ML20055H377
Person / Time
Site:	North Anna
Issue date:	07/19/1990
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20055H378	List: ML20055H377; ML20055H380;
References
	NUDOCS 9007260124
	Download: ML20055H377 (83)
	v • d • e

{{#Wiki_filter:. _ -. '/ >ft280g\\^ UNITED STATES NUCLEAR REGULATORY COMMISSION n t WASHINGTON, O. C. 20555 \\...../ VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO.-50-338 NORTH ANNA POWER STATION. UNIT NO, 1 AMENDMENT TO FACILITY OPERATING LICENSE. Amendment No. 130: License No NPF-4 1. The Nuclear Regulatory Comission (the Comission) has' found that: A. The application for amendment by Virginia Electric and Power Company et al., (9,e licensee) dated May 21, 1990,-complies with the standards ij 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. 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 of the Comission's regulations and all applicable requirements have been satisfied.- 1 9007260124 900719 PDR ADOCK 03000338 P PDC

2. Accordingly, the license is amended by changes to the Technical Speci. fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4.is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained-in Appendices A and B, as' revised through Amendment No.130, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.- 3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days. FORKHENUCLEAR l ULATORY COMMISSION CLv rbert ( erkow, Director Project ir ctorate II Divisio Reactor Projects - I/II Office o Nuclear Reattor Regulation

Attachment:

Changes 1to the-Technical Specifications Date of Issuance: July 19, 1990 i l .A

~;- ATTACHMENT TO LICENSE AMENDMENT NO.130 TO FACILITY OPERATING LICE'NSE NO. NPF-4' DOCKET NO. 50-338 Replace the_following pages of the Appendix "A" Technical Specifications with the enclosed pages as-indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness. Page la IV XI XVII XX 4 1-5 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-62 through 3/4 3-71 (Deleted) 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4-11-5 3/4 11-6 3/4 11-7 through 3/4 11-19 (Deleted) 3/4 12-1 3/4 12-2 through 3/4 12-14 (Deleted) B 3/4 3-4 8 3/4 11-1 B 3/4 11-2 B 3/4 11-3 B 3/4 11-4 through B 3/4 11-6 (Deleted) B 3/4 12-1 6-13b(new)(Deleted) B 3/4 12-2 6-13c (new) 6-19 6-20 6-21 6-23 6-25: 6-26

c o 1 e l INDEK DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Action............................................................. 1-1 Axial Flux Difference............................................. 1 - 1, Channel C411bration................................................ 1-1 L Channel Check...................................................... 1-1 Channel Functional Test............................................ 1-1 Containment Integrity............................................. 1-1 Controlled Leakage................................................. 1-2 Core Alteration.................................................... .1-2 Dose Equivalent I-131.............................................. 1-2 I-Average Disintegration Energy.................................... 1-2 Engineered Safety Teature Response Time............................ 1-3 Trequency' Notation................................................. 1-3 Gaseous Radvaste Treatment System.................................. 1-3 Identified Leakage................................................. 1-3 Member (s) of the Public............................................ 1-3 Offsite Dose Calculation Manual (0DCM)............................. 1-4 O p e ra b le - Op e rab ili ty............................................. 1-4 Operational Mode - Mode............................................ 1-4 Physics Tests...................................................... 1-4 P r e s su re Bo u n da ry Le a ka g e.......................................... 1-4 Process Control Program (PCP)...................................... 1-4 P u r g e -Pu r g i n g...................................................... 1-4 Quadrant Power Tilt Rat1o.......................................... 1-5 NORTH ANNA - UNIT 1 I Amendment No. 46

l + LINDEX (Cont'd) - SECTION PAGE _1. 0 DEFINITIONS (Continued) R a t e d T h e rm a l P o w e r.............................................. 1 - 5 e Reactor Trip System Response Time................................ 1-5 R e po r t a bl e E v e n t................................................. 1 - 5 S hu td own Ma r g i n.................................................. 1 - 5 i Site Boundary.................................................... 1-5 S l a v e R e l ay Te s t................................................. 1 - 5 l -l Source Check..................................................... 1-5 S ta gg e r e d Te x t Ba s i s............................................. 1 - 6 Thermal Power.................................................... 1-6 U ni de n ti fi ed Le a ka ge............................................. 1 - 6 I Unrestricted Ares................................................ 1-6 Ventila tion Exhaus t Trea tment Sys tem............................. 1-6 i .i Venting.......................................................... 1-6 4 1 f i i NORTH ANNA - UNIT 1 la Amendment No. (3,63,325,130,

4

.~.

e f INDEX ( LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i _SECTION PACE i 3/4.2 P0'a*ER DISTRIBUTION LIMITS i 3/4.2.1 Ax i a l F l ux D i f f e r e n c e..................................3 / 4 2 - 1 3/4.2.2 Heat Flux Hot Channel Factor............................ 3/4 2-5 3/4.2.3-Nuclear Enthalpy Hot Channel Factor..................... 3/4 2-9 3/4.2.4 Quadrant Powe r Tilt Ra tio.....................~.......... 3 /4 2-12 3/4.2.5 D N B P a r am e t e r s.......................................... 3 '/4 2 - 14 i 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 INSTRUMENTATION .......................................... 3/4 3-15 3/4.3.3 MONITORINO INSTRUMENTATION Radiation Monitoring.................................... 3/4 3-35 Movable Incore Detec tors................................ 3 /4 3-39 Seismic Instrumentation................................. 3/4 3-40 Me teorological Instrumenta tion.......................... 3 /4 3-43 Auxiliary Shutdown Panel Moni:oring Instrumentation..... 3/4 3-46 Accident Monitoring Instrumentation..................... 3/4 3-49 j Fire De t ec tion Ins t rumen ta tion.......................... 3 /4 3-5 2 Loose Parts Monitoring System.......................... 3/4 3-56 Explosive Gas Moni toring Instrumenta tion............... 3/4 3-59 1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.I REACTOR COOLANT LOOPS AND COOLANT CIRCUI.ATION S tartup and Powe r Operation............................. 3 /4 4-1 Hot Standby............................................. 3/4 4 S hu t d o wn................................................ 3 / 4 4 - 3 Isolated Loop........................................... 3/4 4-4 Isolated Loop Startup................................... 3/4 4-5 NORTH ANNA - UNIT 1 IV Amendment No. 3,10, 32, 4 $, 195,

130,

r J g g

UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTON M

3/4.11 RADIOACTIVE STOR AGE e 3/4.11.1 UQUID STORAGE Liq u id H o ld u p T a n k s....................................................................... 3/4 11 2 3/4.11.2 CASSTORMIE I E x p lo s iv e G a s M i x t u r e................................................................... 3/4 11 4 G a s S to r a g e Ta n k s........................................................................... 3/4 11 5 1 1 NORTH ANNA UNIT 1 XI Amendment No. M 130,

.S INDEX BASES-SECTION i Page 3/4.0 APPLICABILITY.............................................. B 3/4 0-1 { 3/4.1 REACTIVITY CONTROL SYSTEMS i i 3/4.1.1 BORATION CONTR0L'........................................ B 3/4 1-1 3/4.1 2 BORATION SYSTEMS........................................ B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES..............................- B 3/4 1-4 3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................................... B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACT 0RS......................................... B 3/4 2-4 j 3/4.2.4 QUADRANT POWER TILT RATI0............................... B 3/4 2-5 3/4.2.5 DNB PARAMETERS.......................................... B 3/4 2-6 i NORTH ANNA - UNIT 1 XII Amendment No.#1 % ) 165 l l

1. I. g i SECTON E T411 RADIOACTIVE STORAGE 3/4.11.1 U Q U I O S T O R A G E........................................................................, B - 3/4.11 2 3 / 4.1 1. 2 ' G A S S TO R AG E................................................................................ B-3/4 11 3 i i i NORTH ANNA. UNIT 1 XVil Amendment No. 4.130, I t

INDEX. i DESIGN FEATURES SECTION PAGE 5.1 ' SITE . Exclusion Ares.............................................. 5-1 i Low Population Zone......................................... 5-1 Map Defining UNRESTRICTED AREAS Tor Radioactive Gaseous and L Liquid Effluents............................................ 5-2 5.2 CONTAINMENT Configuration.....'.......'................................... 5-1 l Design Pressure and Temperature.............................. 54 5.3 REACTOR CORE Fuel Assemblies............................................. 5-4 Control Rod Assemblies...................................... 5-4 5.4' REACTOR COOLANT SYSTEM Design Pressure and Temperature..........'................... 5-4 Volume...................................................... 55 5.5 METEOROLOGICAL TOWER LOCATION......................'......... 5-5 5.6 FUEL STORACE l l~ Criticality................................................. 5-5 Drainage....................................................~ 5-6 Capacity..................................................... 5-6 5.7 COMPONENT CYCLE OR TRANSIENT LIMIT.......................... 5-6 L NORTH ANNA - UNIT 1 XVIII Amendment No.13 l

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY................................................ 6-1

6. 2 ORGANIZATION 0ffsite.......-..................................................

6-1 Facility Staff.................................................. 6-1 Safety Engineering Staff........................................ 6-la Shift Te'chnical Advisor......................................... 6-la 6.3 FACILITY STAFF QUALIFICATIONS,................................ 6-5 6.4 TRAINING................. 6-5

6. 5 REVIEW AND AUDIT-6.5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)

Function.............. 6-5 Composition....................................,,,,,,,,,,,,,,,,, g.g A1ternates.......................,,,,,.,,,,,,,,,,,,,,,,,,,,,,,,, g.g Meeting Frequency............................................... 6-6 Quorum..............................,,,,,,,,,,,,,,,,,,,,,,,,,,,, g.g Responsibilities................................................ 6-6 Authority....................................................... 6-7 Records.......................,,,....,.,,,,,,,,,,,,,,,,,,,,,,,,,, s.7 6.5.2 SAFETY EVALUATION AND CONTROL (SEC) Function........................................................ 6-7 Composition..................................................... 6-8 NORTH ANNA-UNIT 1 XIX Amendment No. 30, 4 8 l

INDEX i ~ ADMINISTRATIVE CONTROLS l l i SECTION PAGE Consultants................................................. 6,8 j Meeting Frequency........................................... 6-8 Review..................................................... 6-8 Authority................................................... 6-9 Records'.................................................., 6 ' 6.5.3 QUALITY ASSURANCE DEPARTMENT 1 F. unction..-...........-....................................... 6-10 j u t h o r i ty................................................... 6 i. 1 ( Records'..................................................... 5-11 i 6.6 REPORTABL E EVENT ACTION...................................... 1 6.7 SAFETY LIMIT VIOLATION ........................................_6 12 l 6.8 P ROC EDU R E S AN D PROGRAMS................ -...................... ' 6.9 REPORTING REQUIREMENTS i 1 6.9.1 ROUTINE REPORTS........................................... 6-14 6.9.2 SPECIAL REPORTS........................................... 6-21 6.10 RECORD RETENTION........................................... 6 6.11 RADIATION PROTECTION PROGRAM............................... 6-24 6.12 H IGH RADI AT ION A R EA........................................ 6 -24 6.13 ENVIRONMENTAL QUAL I FICATION................................ 6-25 6.14 PROCESS CONTROL PROGRAM ( PCP ).............................. 6-25 6.15 0FFSITE DOSE CALCULATION MANUAL (00CM)..................... 6-26 NORTH ANNA - UNIT 1 XX Amendment No. 48,53,130,

1 a _.s 1.0 DEFINITIONS (Continued) t ENGINEERED SAFETY TEATURE RESPONSE TIME 1.11 The ENGINEERED SAFETY TkATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its EST actuation setpoint at the channel. sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their re-quired positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. TREQUENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2. CASEOUS RADWASTE TREATMENT SYSTEX I 1.13 A CASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant offgases from the primary system and providing for delay or. holdup for the system of reducing the total radioactivity prior to release to the purpose q environment. The system is composed of the waste gas decay tanks, regenerative heat exchanger, vaste gas charcoal filters, vaste gas surge tanks and,vaste gas diaphram compressor. process vent blowers, IDENTIFIED LEAKAGE 1.14-IDENTIFIED LEAKAGE shall be: Leskage (except CONTROLLED LEAKAGE) into closed systems, such a. as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or Reactor coolant system leakage through a steam generator to c. the secondary system. MEMBER (S) 0F THE PUBLIC l 1.15 MEMBER (S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are permitted to use a I portions of the site for recreational, occupational, or other purposes not essociated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job i function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation : and radio-cetive materials. NORTH ANNA - UNIT 1 1-3 Amendment No.16, 4 8

l 1 L 1.0 DEFINITIONS (Continued) STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist oft A test schedule for n systems, subsystems, trains or other a. i designated components obtained by dividing the specified test interval into a equal subintervals, j j b. The testing of one system, subsystea, train or oth'er designated-component at the beginning of each subinterval. i THERMAL POWER i 1.33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. j UNIDENTIFIED LEAKAGE 1.34 UNI'DENTIFIED 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 l whero access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area -within the SITE BOUNDARY used for residential quarters or for industrial, ceamarcial, institutional, and/or recreational purposes. VENTILATION EXRAUST TREATMENT SYSTEM 1.36 A VENTILATION EXHAUST TREATMENT SYSTEM is the system designed and l 'l installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vant exhaust gases through-l charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or 1 particulates from the gaseous exhaust stream prior to the release to the i environment (such a system is not considered to have any effect on noble gas affluones). Engineered Safety Feature (EST) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. i VENTING 1.37 VENTING is the controlled process of dischargias air or gas from a I i confinement to maintain temperature, pressure, humidity, concentration or othat operating condition, in such a manner that replacement at: or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. B, NORTH ANNA - UNIT 1 1-6 Amendment No. 26, lg g,.125

i I I 30 ' 1 c I Soecification 3/4.3.3.10 has been deleted I\\ NORTH ANNA UNIT 1 3/4 3 58 Amendment No. 48,63,130, f i A a m___.__-_____ L i 1 INSTRUMENTATION l EXPLOSIVE GAS MONITOR!NG INSTRUMENTATION. l 1 UMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table 3.314 shall ) be OPERABLE with their alarm / trip selpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded. l' APPLICABILITY: As shown in Table 3.314, ACTION:

a. With an explosive gas monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, declare the channel inoperable, and take the ACTION shown in Table 3.314

b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, for reasons other than a above, take the ACTION shown in Table 3.3 14. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why the inoperability was not corrected in a timely. manner,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REOUIREMENTS - 4.3.3.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.314. l l: l~ i l l l NORTH ANNA UNIT 1 3/4. 3 59 Amendment No.18,130, 1 s _i_., t,.

}'- e TABLE 3 314 EXPLOSIVE GAS MONITORING INSTAUMENTATION - MINIMUM CHANNELS INSTRUMENT 'OPEAABLE A PDLIC ABILITY ACTON 1. DELETED 2. WASTEGAS HOLDUP SYSTEM EXPLOSlVE GAS MONITORING SYSTEM (Shared with Unit 2) a. Hydrogen Monitor 1 32 b. Oxygen Monitor-1 32 During process vent system operation (treatment for primary system offgases). j i i ACTION 32 r With the number of channels OPERABLE less than required by the minimum-channels OPERABLE requirement, operation of this system may continue for up to 14 days provided grab samples are taken and analyzed daily. With this channel inoperable, operation may continue provided grab samples are taken - I and analyzed: (1) every 4 hours during degassing. operations and (2) daily i during other operations. t 1 -) i l NORTH ANNA UNIT 1 3/4 3 60 Amendment No. 4,130,

o TABLE' 4.314 i } EXPLOSIVE GAS MONITORING INSTRUMENTATIOM SURVEILLANCE REQUI AEMENTS' CHANNEL MODES IN WHICH CHANNEL SME ' CHANNEL FUNCTIONAL SURVEILLANCE - INSTAUMENT -CHECK CHECK CAllBRATION TEST AEQUIRED-

1. DELETED

2. WASTE GAS HOLDUP -

SYSTEM EXPLOSIVE GASMONITORING SYSTEM l

a. Hydrogen Monitor D

N.A. O(3) M

b. Oxygtn Monitor 0

N.A. Q(4) M I During process vent system operation (treatment for primary system offgases) i ( 3 ) The CHANNEL CAllBRATION shall include the use of standard gas samples containing a i nominal: f

1. One volume percent hydrogen, balance nitrogen, and

2. Four volume percent hydrogen, balance nitrogen.

(4 ) The CHANNEL CAllBRATION shallinclude the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen.

4 s l j NORTH ANNA UNIT 1 3/4 3 61 Amendment No, f 8,130, l

i L. 4 Specifications 3/4.11 1'1 through 3/4,11.1.3 have been-deleted NORTH ANNA UNIT 1 3/4 11 1 Amendment No. AB 63,130,

i I RADOACTIVE STORAGE ' LlOUID HOLDUP TANKS UMrTING CONDITION FOR OPERATION I 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved y or entrained noble gases, a. Refueling Water Storage Tank. b. Casing Cooling Storage Tank i c. PG Water Storage Tank'- d. Boron Recovery Test Tank

e.

Any Outside Temporary Tank" APPLICABILITY: At all times, j ACTION: i i 4 With the quantity of radioactive materialin any of the above listed tanks exceeding a. the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. 1 SURVEILt.ANCE REQUIREMENTS = 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per week when radioactive materials are being added to the tank. i' 'This is a shared system with Unit 2. " Tanks included in this Specification are those cutdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area crains connected to the liquid radwaste ion exchanger system. NORTH ANNA UNIT 1 3/4 11 2 Amendment No. 4, 1303 /

4 I v 1 41 l, s i Specifications 3/4.11.2.1' through 3/4.11.2.4 have been deleted 3 ' l l I NORTH ANNA UNIT 1 3/4-11 3 Amendment No. 4.130,

..-_. 1

RADIC) ACTIVE STORAGE i 3/4.11.2 GAS STORAGE EXPLOS!VE GAS MfXTUAE i LIMITING CONDITION. FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas decay tanks shat) be limited to less than ] or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume and is j less than 96% by volume, APPLIC ABILITY: At all times. ACTION:

a. With the concentration of oxygen in the waste gas decay tanks greater than 2% by i

volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours.

b. With the concentration of oxygen in the waste gas decay tanks greater than 4% volume l

and the hydrogen concentration greater than 2% by L'ume, immediately suspend all - additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by. volume without delay,

c. The' provisions of Specifications 3.0.3 and 3.0.4 are not applicable, i

. SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas decay tanks shall be determined to be within the above limits by continuously monitoring-the waste gases in the waste gas decay tanks with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-14 of Specification 3.3.3.11. A NORTH ANNA UNIT 1 3/4 11 4 Amendment No. 48, 130, I

i RADOACTIVE STORAGE GAS STCAAGE TAPES UMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to s 25,000 curies noble gases (considered as Xe 133). APPLICABILITY: At all times. ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit.

I

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.11.2.6 The qt antity of radioactive material contained in each gas storage tank shall be ' determined to be within the above. limit at least once per month when the specific activity of the. primary reactor coolant is s 1.0 nCllgm DOSE EQUIVALENT l.131. Under conditions which result in a specific activity > 1.0 pCi/gm DOSE EQUIVALENT l 131, the Gas Storage Tank (s) shall be sampled once per 24 hours, when radioactive materials are being added to the tank, t I NORTH ANNA. UNIT 1 3/4 11 5 Amendment No. AB.13Q,

8 0 l i j i (. ? I t = I Specifications 3/4.11.3 through 3/4.11.4 have been deleted . 1 j = = NORTH ANNA UNIT 1 3/4 11 6 Amenament No. #B.130, k-

i i l j i I i i i i Specifications 3/4.12.1 through 3/4.12.3 have been deleted E + NORTH ANNA UNIT 1 3/4 12 1 dment No. 48,63,

, INSTRUMENTATION B_ASES r 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION' The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. 3/4.3.3.7 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 wil.1 reduce the poten-tial for damage to safety related equipment and is an integral element in the overall facility fire protection program. In t inoperablhe event that a portion of the fire detection instrumentation is e, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable i instrumentation is restored to OPERABILITY. l t 3/4.3.3.9 LOOSE PARTS MONITORING SYSTEM OPERABILITY of the Loose Parts Monitoring System provides assurance that loose parts within the RCS will be detected. This capability is designed to ensure that loose parts will not collect and create undesirable flow blockages. NORTH ANNA - UNIT 1 B 3/4 3-3 Amendment No. 3,)& 105

i This Page intentionally Left Blank h NORTH ANNA UNIT 1 B 3/4 34-Amendment No. 48. 130,

i 4 1 i 4 Speedications 3/4,11 1.1 through 3/4.11.1.3 have been deleted 4 i NORTH ANNA. UNIT 1 B 3/4 11 1 Amendment No. #8. 130, t

RADCACTfVE STORAGE l'd 11.1 LtOUID ITOR AGE EMSES 3/4.1114 L'OUID WOLDUP TANKS The tanks listed in this Specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B. Table ll, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA. 4 Specifications 3/4.11.2.1 through 3/4.11.2.4 have been deleted. NORTH ANNA UNIT 1 B 3/4 11 2 Amendment No. $8, 130, A*/

j RADCACTfVE MORAGE T411.2 GAS STORAfag BASES T4112 s EyptosivE gas M!xTUAE This Specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. T4112 6 GAS STORAGE TANKS The tanks included in this Specification are those tanks for which the quantity of radioactivity contained is not limited directly of indirectly by another Technical Specification to a quantity that is less than the quantity which provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at 4 the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent wdh Branch Technical Position ETSB 115 in NUREG 0800, July 1981. Specifications 3/4.11.3 and 3/4.11.4 have been deleted, l l l l NORTH ANNA UNIT 1 B 3/4 11 3 Amendment No.18,130,

'\\ 1 Specifications 3/4.12.1 through 3/4.12.3 nave been deleted NORTH ANNA UNIT 1 g 3/4 12 1 Amendment No. 48, 130, 1

ADMINISTRATIVE CONTROLS e. Radiometive EHluent Centreft procram A program shall be provided conforming ith 10 CFR 50.36a for the Control ( radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable, The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shallinclude remedial actions to be taken whenever the program limits are exceeded. The program shallinclude the following elements: 1 ) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2 ) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B. Table ll, Column 2, 3 ) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the

OOCM, 4 ) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioacWe materials in liquid effluents released from each unit to UNRESTRICTED AREA'3 conforming to Appendix I to 10 CFR Part 50, 5 ) Determination of cumulative and projected dose contributions from radioactive effluents for the currer.t calendar quarter and current calendar year in accordance with the meQodology and parameters in the ODCM at least every 31

days, 6 ) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix i to 10 CFR Part 50, 7 ) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B. Table 11, Column 1, NORTH ANNA. UNIT 1 6 13 b AmendrientNa 130,

ADMINISTAATIVE CONTAOLS B) Limitations on the annual and Quarterly air doses resulting from ncble gases released in gaseous effluents from each snit to areas beyond the SITE BOUNARY conforming to Appendix 1 to 10 CFR Part 50, 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine 131, lodine,133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to re' cases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Radioloeical Environmental Monitorino Or gLeg,g g f r A

program shall be 'provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways, The program shall (1) be coniained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

CDCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. NORTH ANNA UNIT 1 6 13 c Amendment No. 130, ^'

i \\. ADMINISTMTivE CONTAOLS 8) Limitations on the annual and quarterly air doses resulting from noble cases released in gaseous effluents from each onit to areas beyond the SITE BOUNARY conforming to Appendix i to 10 CFR Part 50, l-9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine 131, lodine 133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from i enh unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 30 CFR 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE l

PUBLIC due to releases of radioactivity and to radiation from uranium fuel i cycle sources conforming to 40 CFR Part 190. l l l f. Aadieleeleni Environmental Monitorine oreeram A ' program shall be 'provided to monitor the radiation and radionuclides in the i environs of the plant. The program shall provide (1) representative measurements l of radioactivity in the highest potential exposure pathways, and (2) verification of l the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform I l to the guidance of Appendix 1 to 10 CFR Part 50, and (3) include the following: 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and pararneters in the

OOCM, l

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and + 3) Participation in a interlaboratory Comparison Program to ensure that independent checks _on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as ps" of the quality assurance program for environmental monitoring. 1 1 NORTH ANNA UNIT 1 6 13 c Amendment No. 130, i .s.

ADMINISTRATIVE CONTAOLO (Continued) ANNUAL RADIOLOGICAL ENV!RONMENTAL OPERATING REDORT' 6.9.1.8 The Annual Radiological Environmental Operat'ing Report covering the operation of the unit during the previous calendar year snall be submitted bef re May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the OOCM and (2) Sections IV.S.2, IV.B.3.and IV.C of Appendix 1 to 10 CFR Part 50. d i + ~~ ~in~gIe~5u~brniiial r55ay~EE~rna~ditor a multiple unit station. ~ ~ 'As l NORTH ANNA UNIT 1 6 19 Amendment No. 37,Jg,pp,g), 105, 130, N

ADMINISTRATIVE CONTROL.S ( C o n t i nu e d ) SEMIANNLIAL RADIOLOGICAL EFFLUENT mELEASE REDO 8%T' 6.9.1.9 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The matenal provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. l

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste. systems, the submittal shall specify the releases of radioactive material from each unit.

NORTH ANNA UNIT 1 6 20 Amendment No. 48,63,130, i th

E 1 ADMINISTRATIVE CONTROLS (Continued) SPECIAL REDORTE [ 6.9.2 Special reports shall be submitted to the Regional Administrator, Region 11. within the time period specified for each report. These reports shall be submitted pursuant to the requirement of the applicable specification:

a. Inservice Inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion.

b. MODERATOR TEMPERATURE COEFFICIENT. Specircation 3.1.1.4.

c. RADIATION MONITORING INSTRUMENTATION. Specification 3.3.3.1, Table 3.3 6.

Action 35.

d. SEISMIC INSTRUMENTATION. Specifications 3.3.3.3 and 4.3.3.3.2.

e. METEOROLOGICAL INSTRUMENTATION. Specification 3.3.3.4.

f. FIRE DETECTION INSTRUMENTATION. Specification 3.3.3.7.

g. LOOSE PARTS MONITORING SYSTEMS. Specification 3.3.3.9.

h. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Specification 3.4.8.

i. OVERPRESSURE PROTECTION SYSTEMS. Specification 3.4.9.3.

j. EMERGENCY CORE COOLING SYSTEMS. Specircation 3.5.2 and 3.5.3.

k. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.

1. GROUND WATER LEVEL. SERVICE WATER RESERVOIR. Specifcation 3.7.13.

m. FIRE SUPPRESSION SYSTEMS. Spscification 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4, and 3.7.14.6.

i

n. RADIOACTIVE EFFLUENTS As required by the ODCM.

o. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM.

p. SEALED SOURCE CONTAMINATION. Specircation 4.7,11.1.3.

q. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specircation 4.4.10. For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during the performance of Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.

NORTH ANNA UNIT 1 6 21 Amendment No. 3. A8,83. 78.783.130, l

) il' l ADMINISTRATIVE CONTROLS i r. CONTAINMENT STRUCTURAL INTEGRITY. Specification 4.6.1.6. For any L abnor il degradation of the containment structure detected during the performance of Specification 4.6.1.6, an initial report shall be submitted within 10 days after the completion of Specification l 4.6.1.6. A final report..which includes (1) a description of the i condition of the liner plate and concrete, (2) inspectioa l-procedure, (3) the tolerance on cracking, and (4) the corrective actions taken, shall be submitted within 90 days after the completion of Specifi-i cation A.6.1.6. 6.10 RECORD RETENTION i 6.10.1 The following records shall be retained for at least five years: Records and logs of facility operation covering time interval at a. i each power level. b. Records and loos of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c. ALL REPORTABLE EVENTS and Special Reports, i d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications. Records of changes made to Operating Procedures. e. f. Records of radioactive shipments. g. Records of sealed source leak tests and results, h. Records Of annual physical inventory of all sealed source material of record, i. Records of the annual audit of the Station Emergency Plan and implementing, procedures, f. Records of-the annual audit of the Station Security 81an and ~ implementation procedures. r 6.10.2 The following records shall be retained for the duration of the 9 Facility Operating License: i PORTH ANNA - UNIT 1 6-22 Amendment No. 3.48,63,78, 103 e---w*" r W v ww-w* 't'

i ADMINISTRATIVE CONTROLS Records and drawing changes refleeting facility design modifications a. made to systens and equipment described in the Final Safety Analysis Report. b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. Records of facility radiation and centsNnation surveys, c. d. Records of radiation exposure.for all individuals entering radiation control areas. Records of gaseous and liquid radioactive material released to the e.

environs, f.

Records of transient operational cycles for those facility components identified in Table 5.9-1. g. Records of reactor tests and experiments. h. Records of training and qualification for current members of the plant,ta f f. 1. Records of in-service inspections performed pursuant to these Techni-cal Specifications, j. Records of Quality Assurance activities required by the QA fianual. k. Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59. 1 Records of meetings of the SNSOC. Records of meetings of the Systein Nuclear' Safety and Operating m. Committee to issuance of Amendment No. 30. Records of the service lives of all hydraulic and mechanical snubbers n. required to be OPERABLE by Technical Specification 3.7.10 including the date at which the service life comences and associated installa-t' ion and maintenance records, Reco,ds of secondary water sampling aid water quality, o. j p. Records of Environmental Qualification which are covered under the i provision; of Paragraph 6.13. l q. Records of analyses required by the radiological environmental moni-toring program that would permit evaluation of the accuracy of the analysis at a later date. This would include procedures effective at specified times and QA records showing that these procedures were followed. l r. Records of reviews performed for changes made to the OFFSITE DOSE - CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. NORTH ANNA - UNIT 1 6-23 Amendment No. 38,33,48,77,

130,

ADMINISTRATIVE CONTROLS ) l 6.11 RADIATION Pe0TECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-i sittent with the requirements of 10 CFR Part 20 and shall be aporoved, maintained and adhered to for all operations involving personnel radia- { tion exposure. 6 1 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mres/hr but less than 1000 arem/hr shall be barricaded and conspicuously posted as a high i i radiation area and entrance thereto shall be controlled by requiring l issuance of a Radiation Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following: { y A radiation monitoring device which continuously indicates 4. the radiation dose rate in the area. b. A radiation monitoring device which continuously integrates [ the radiation dose rate in the area and alarms when a preset integrated dote is received. Entry into such areas with this monitoring device may be made after the dose rate level i in the area has been established and personnel have been made knowledgeable of them, i c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate r initoring device. [ This individual shall be responsible for Graviding positive control over the activities within the area and shall perform periodic radiation sueveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit. 6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than i 1000 mrom/hr. In addition, locked doors shall be provided to prevent r unauthorized entry into such areas and the keys shall be maintained l under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist. t "nealth Physics personnel shall be exempt from the RWP issuance require-I ment during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas. ~, NORTH ANNA - UNIT 1 6-24 .<iarantNo.16,44,.g3l

o 1 ADMINISTRATIVE CONTROLS 6.13 DELETED i 6.14 D AOCESS CONTAOL P AOGRAM IPCP) 6.14,1 Cnanges to the PCP:

1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2,r, This documentation shall contain:

8 a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, t

2. Shall become effective after review and acceptance by.the SNSOC and the approval of the Plant Manager.

1 NORTH ANNA UNIT 1 6 25 Amendment No, J8.183,130.

ADMINISTRATIVE CON ~AOLS 615 OFSITE DOSE CALCULATION MANUAL (ODCM) Changes to the ODCM: a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.r. This documentation shall contain: i 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and i 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106. 40 CFR Part 190,10 CFR 50.36a, and Appendir i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. b. Shall become effective after review and acceptance by the SNSOC and the approval of the Plant Manager, c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was mace. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the date (e.g., month / year) the change was iniplemented. 6.16 DELETED l l l NORTH ANNA. UNIT 1 6 26 Amendment No. #8,130, 4

, '(( Io,, UNITED STATES ,3 p, NUCLEAR M GULATORY COMMISSION 5' 'l WA&MINGTON. D. C. 20666 \\...../ t VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. NPF-7 r 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Virginia Electric and Power Company, etal.,(thelicensee)datedMay 21, 1990, 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. Thereisreasonableassurance(1)thattheactivitiesauthorized 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 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 Comission's regulations and all applicable requirements have been satisfied. 1

2 2. Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.130 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days. i FOR THE NU LEAR REG TORY COMMISSION / Herbert N. erkow, Director U Project D r ctorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications i Date of Issuance: July 19, 1990 4 9 I

ATTACHMENT TO LICENSE AMENDMENT N0. 114 .4 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment nue er and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document i completeness. Page la IV X XIVa XV11 1-4 1-5 3/4 3-51 3/4 3-52 3/4 3-53 3/4 3-54 3/4 3-55 through 3/4 3-66 (Deleted) 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-6 3/4 11-7 through 3/411-19(Deleted) 3/4 12-1 3/4 I?-2 through 3/4 12-14 (Deleted) B ",/4 3-4 03/411-1 F 3/4 11-2 8 3/4 11 3 8 3/4 11-4 throughB3/411-6(Deleted) B 3/4 12-1 B3/412-2(Deleted) 6-13b(new) 6-13c (new) 6-19 6-20 6-21 6-23 6 25 6 26 1 4

INDEX l DEFINITIONS S ECTIO.N. PAGE 1.0 DErtNITIONS t Act1on............................................................. 1-1 Axial Flux Difference............................................ 1-1 Channel Calibration................................................ 1-1 Channel Check...................................................... 1-1 Channel Tunctional Test............................................ 1-1 Containment Intergrity............................................. 1-1 1 C o n t r o l l e d L e a ka g e................................................. 1-2 i Core Alteration.................................................... 1-2 Dose usuivalent I-131.............................................. 1-2 I-Average Disintegration Energy.................................... 1-2 Engineered Safety Teature Response Time............................ 1-3 Trequency Notation................................................. 1-3 Gaseous Radwaste Treatment System.................................. 1-3 Identified Leakage................................................. 1-3 i Member (s) of the Pub 11c............................................ 1-3 Offsite Dose Calculation Manual (0DCM)............................. 1-4 Operable - Operability............................................. 1-4 Operational Mode - Mode............................................ 1-4 Physics Tests...................................................... 1-4 P r e s su re Bound ry Le aka g e........................................... 1-4 Process Control Program (PCP)...................................... 1-4 Purge-Purging...................................................... 1-4 Qu a d ran t P owe r T il t Ra t i o.......................................... 1-5 i NORTH ANNA - UNIT 2 I Amendment No. 31 i 1 , /*. ~

O 1NDEX(Cont'd) SECTION PAGE 1.0 OEFINITIONS (Continued) Rated thermal Power.............................................. 1-5 Reactor Trip System Response Time................................ 1-5 R e po r t a bl e E v e n t................................................. 1 - 5 Shutdown Margin.................................................. 1-5 Site Boundary.................................................... 1 5 Slave Relay Test................................................. 1-5 Source Check..................................................... 1 5 S ta gge r ed Tex t Ba s i s............................................ 1 - 6 Thermal Power.................................................... 1 6 U ni d e nt i f i ed l e$ k a g 9.............................................. l - 6 Unrestricted Area................................................ 1-6 Ventila tion Exha us t Trea tment Sys tem............................. 1 6 Venting..........................................................-1 6 l NORTH ANNA UNIT 2 la Amendment No. 37.47.709. 114.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENT ( SECTION PACE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference.................................. 3/4 2-1 3/4.2.2 Heat Flux Hot Channel Tactor........................... 3/4 2-5 3/4.2.3 Nuclear Enthalpy Hot Channel Tactor.................... 3/4 2-9 3/4.2.4 Quad ran t Powe r Tilt Ra tio.............................. 3/4 2-12 3/4.2.5 DNB Parameters......................................... 3/4 2-15 1 1 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.................... 3/4 3-1 3/4.3.2 ENGINEERED SATETT TEATURE ACTUATION SYSTEM I N S TR UM EN T AT I O N........................................ 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring................................... 3/4 3-38 Movable Incore Detectors............................... 3/4 3-42 Auxiliary Shutdown Panel Monitoring Instrumentation..... 3/4 3-43 Accident Monitoring Instrumentation.................... 3/4 3-46 Tire Detection Instrumentation......................... 3/4 3-49 I Explosive Gas Moni toring Instrumentation............... 3/4 3 52 3/4.4 REACTOR COOLANT SYSTEH 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power operation........................... 3/4 4-1 Bot Standby........................................... 3/4 4-2 Shutdown.............................................. 3/4 4-3 i Isolated Loop......................................... 3/4 4-4 i Isolated Loop Startup................................. 3/4 4-5 1 l 4 NORTH ANNA - UNIT 2 IV Amendment No. d/1.ff,114,

i t i l L!>I7tNG CON 0fffCNS 80R C#ttaffCN ANO $URVE!LLANCE RECVIREMENT$ I t $tCTICN I l 3/4.9 REFVfLING CPERATICNS i 3/4.9.1 80 RC N CC NCINTRATI C N........................................ 3/4 9-1 i 3/4.9.2 INSTRUMENTATION............................................ 3/4 9 2 3/4.9.3 DECAY TIME................................................. 3/4 9 3 I 3/4.9.4 CONTAINMENT SUILDING P ENETRATICNS.......................... 3/4 9 4 3/4.9.5 COMMUNICATICN$............................................. 3/4 9 6 3/4.9.6 MANIPULATOR CAAh! CPERA81LITY.............................. 3/4 9, r 3/4.9.7 C RANE TRAVEL - $P ENT FUtl P 17.............................. 3/4 9*$ l 3/4.9.8 RESIDUAL HEAT Rt.MVAL AND COOLANT CIRCULATICN . A l l Wa t e r L e v e 1 s........................................... 3/4 9 9 f Low Water Leve1............................................ 3/4 9-9a 3/4.9.9 CONTAINMENT PURCE AND EXHAUST !$CLATION $YSTEM............. 3/4 9 10 1 3/4.9.10 WATER LEVEL REACTOR VES$tL................................. 3/4 9 11 I 3/4.9.11 $ PENT FUEL PIT WATIA LEVEL................................. 3/4 9-12 3/4 9.12 FUEL SUILD!HG VENTILATICN SYSTEN........................... 3/4 9-13 3/4.10 $PECIAL'it37 EXCEP?tCNS 3/4.10.1 $HUTDCWN' MARGIN............................................ 3/4 10-1 3/4.10.2 GRCUP HEIGHT IN$tRTION AN0 POWEA O!$7RIBUTION.............. 3/4 10 2 3/4.10.3 PHYSICS TI$T...................................'............ 3/4 10 3 3/4.10.4 REACTOR COOLANT LCCP$...................................... 3/4 10-4 3/4.10.5 PC$1TICN IN0!CATOR CHANNELS-SHUTDChN....................... 3/4 10-5 I NCRTH t.NNA UNIT 2 IX l l l e e. ..e e 8 0-- -.-~..-m

gggg 4 UMITING CONDITIONS FOR OPERATION AND SURVEIU.ANCE REOUtAEMENTS t SECTION pg 1411 AADICACT!VE STOAAGE 3/4.11.1 UQUID STOPAGE Uq u id H old u p T a n k s....................................................................... 3/4 11 2 e 3/4.11.2 GASSUW3E E x pio s iv e G a s Mi x t u r e................................................................... 3/4 11 4 G a s S tor a g e T a n k s.......................................................................... 3/4 11 5 c i l l NORTH ANNA UNIT 2 X Amendment No. U,114,

.. ~.. -.. _. la ~ f l l M EASES SECTION p42 T4.11 mADIOACTIVE STOAAGE 3/4.11.1 LI O U l O S T O R A G E......................................................................... B 3/4 112 3/4.11.2 G A S S T O R A G E............................................................................... B 3/4 11 3 1 I l l l l l I l l l NORTH AN."A. UNIT 2 XIVa Amendment No. 37. ~114,

INDEX. _ ADMINISTRATIVE CONTROLS SECTION PACE Consultants................................................. 6-9 Meeting Trequency........................................... 6-9 Review...................................................... 6-9 9 Authority................................................... 6-10 Records..................................................... 6-10 6.5.3 QUALITY ASSURANCE DETJJtTMENT l Function.................................................... 6-11 l Authority................................................... 6-12 i Records..................................................... 6-12 6.6 REPORTABLE EVENT ACTION..................................... 6-13 6.7 SAFITY LIMIT VIOLATION...................................... 6-13 6.8 PROCEDURES AND PROGRAMS..................................... 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS........................................... 6-14 6.9.2 SPECIAL REPORTS........................................... 6-21 6.10 R E C O RD R E T E N T I O N........................................... 6-22 6.11 RAD I AT I O N P ROTE CT I ON P ROG RAM............................... 6-24 6.12 H I C H RAD I AT I O N A R EA........................................ 6-24 6.13 PROCESS CONTROL PROGRAM (PCP) .............................. 6-25 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) ..................... 6-25 I NORTH ANNA - UNIT 2 XVII Amendment No. JJ, 31, $7,

114,

. ~.

i 1.0 DETINITIONS (Continued) _ ENGINEERED SATETY TEATURE RESPONSE TIME 1.11 The ENGINEERED SATETY TEATURE RESPONSE TIME shall be that time interval from when the sonitored parameter exceeds its EST actuation i setpoint at the channel sensor until the EST equipment is capable of performing its safety function (i.e., the valves travel to their re-quired. positions, pucp discharge pressure 6 reach their required values, etc.). Times shall include diesel generator starting and sequence leading delays where applicable. FREQUENCY NOTATION 1.12 The TREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to.the intervals defined in Table 1.2. CASEOUS RADWASTE TREATMENT SYSTEM t 1.13 A GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed j to reduce radioactive gaseous effluents by collecting primary coolant systen offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. The system is composed of the vaste gas decay

tanks, regenerative heat exchanger, vaste pas charcoal filters, process vent blowers.

l vaste gas surge tanks and.vaste gas diaphram compressor. f 6 IDENTITIED LEAKAGE l 1.14 IDENTIFIED LEAKAGE shall bet Leakage (except CONTROLLED LIAKAGE) into closed systems, such s. i as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRES $URE BOUh9ARY LEAKAGE, or l c. Reactor coolant systes leakage through a steam generator to the secondary system. MEMBER (S) 0F THE PUBLIC 1.15 MEMBER (S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are paraitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall no,t_ include non-employees such as vending machine servicemen or postaan who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radio-active materials. l NORTH ANNA - UNIT 2 1-3 Amendment No. 31 a~ ____.1._

,i 1.0 DEFINITIONS (Continued) I OFSfTE DOSE CALCL'LATION MANUAL 1.16 The OFFSITE DOSE CALCUt.ATION MANUAL (b'OCM) shall contah the methodology and parameters used in the calculation of offsite coses resulting from radioactive gaseous and liquid i effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Naciological Monitoring Program. The ODCM shall also j contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi. annual Radioactive Effluent Release Reports required by Specifications 6.9.1.8 and E.9.1.9. OPERABLE OPEA ALUL!TY 1.17 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing hs specified function (s), and when all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxillary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s). OPERATIONAL MODE. MODE 1.18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1, PWYSICS TESTS 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter l 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission. PRESSUAE 90LINDARY LEAKAGE l 1.20 PRESSURE BOUNDARY LEAKAOE shall be leakage (except steam generator tube leakage) through a non isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall. PAOCESS CCNTAOL PAOGRAM l 1.21 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, l analyses, tests and determinations to be made to ensure that the processing and packaging of solid adioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance veith 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste. PURGE PURGhG 1.22 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purity the confinement. NORTH ANNA UNIT 2 14 Amendment No. U,114,

i., o I _l. 0 DEFfN!Tf0NS' (Continued) 1 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 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. 2'4 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 Tb VACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from 'when the n.iitored paramat 3xceeds its trip setpoint at the channel sensor until loss of stationars ; m per coil voltage. i REPORTABLE EVENT i 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CM Part 50. y i SHUT 00WN 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 leased or otherwise controlled by the licensee.The SITE BOUNDARY shall b SLAVE RELAY TEST l 1,29 A SLAVE RELAY TEST shall be the energization of each slave relay i and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices. SOURCE CHECK l 1.30 A SOURCE CHECK shall be the qualitative assessment of channel -response l when the channel sensor is exposed to radiation. radiation monitoring systems. This applies to installed NORTH ANNA - UNIT 2 S Amendment No. 37,47,774 799,II4'

l - l; 1.0 DEFINITIONS (Continued) STACCERED TEST BASIS i 1,32 A STAGGERED TEST BASIS shall consist oft a. A test schedule for a systems,' subsystems, trains or other. designated components obtained by dividing.the specified test interval into a equal subintervals, b. The testing of one systes, subsystes, train or other designated component at the beginning of each subinterval. THERMAL P0k'ER 1.33 THEPEAL Pok'ER shall be the total reactor core heat transfer rate to the reactor coolant. UNIDENTIFIED LEAKAGE 1.34 UNIDENTIFIED LEAKAGE shall be all leakass which is not IDENTITIED l LEAKAGE or CONTROLLED LEAKAGE. UNRESTRICTED AREA 1.35 An UNRESTRICTED ARIA shall be any area at or beyond the SITE BOUNDARY where access is not controlled by. the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the !,ITE BOUNDARY used for residential quarters or for industrial, commercial. institutional, and/or recreational purposes. VENTILATION EXRAUST TREATMENT SYSTEM 1.36 A VENTILATION EXHAUST TREATMENT SYSTEM is the system designed and l installed to reduce gaseous radiciodine er radioactive material in particulate form in effluents by passing ventilation or. vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on n;ble gas offluents). Engineered ' Safety Teature (EST)- atmospheric cleanup systems' are not considered to be VEN"'ILATION EXHAUST TREATMENT SYSTEM components. VENTING f 1.37-VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature - pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required. during VENTING. Vent, used in system names,- does not imply a VENTING process. l NORTH ANNA - UNIT 2 16 AmendmentNo.gy,109 1

/Y l, I i i - 3 l ' i i l u Specifications 3.3.3.9 and 4.3.3.10 have been deleted. 3.3.3.10 has been changed to 3.3.3.11 . i. NORTH ANNA UNIT 2 3/4 3 51 - Amendment No. g,114,

INSTRUMENTATION EXPLOSlVE GAS MONITORING INSTRUMENTATION UMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas m:11toring instrumentation channels shewn in Table 3.313 sha'l be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded. APPLICABILITY: As shown in Table 3.313 ACTION:

a. With an explosive gas monitoring instrumentt on channel alarm / trip setpoint less conservative than required by the above Specification, declare the channel inoperable.

and take the ACTION shown in Table 3.313.

b. With less than the minimum number of explosive gas monitoring instrumerrtation channels OPERABLE, for reasons other than a above, take the ACTION shown in Table 3.3 13. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why the inoperability was not corrected in a timely manner,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, e

i SURVEILLANCE REOUIREMENTS 4.3.3.11 Each explosive gas monitoring instrumentation. channel shall be demonstrated l OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.313. NORTH ANNA UNIT 2 3/4 3 52 Amendment No. H,114,

TABLE 1313. EXPLOSIVE GAS MONITORING INSTAUMENTATION i MINIMUM CHANNELS INSTAUMENT _ OPEAABLE APDLICABILITY ACTION 1; DELETED 2. WASTE GAS HOLOUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM (Shared with Unit 2) ) j a. Hydrogen Monitor 1 32 b. Oxygen Monitor 1 32 " urin.g process vent system operation (treatment for primary system offgases). ACTION 32 - With the numoet of channels OPERABLE fess than required by the minimum channels OPERABLE requirement, operation of this system may continue for up to 14 days provided grab samples are taken and analyzed' daily, With this channel inoperable, operation may continue provided grab samples are taken and analyzed: (1) every 4 hours during degassing operatioq and (2) daily during other operations. i NORTH ANNA UNIT 2 3/4 353 Amendment No. 37,(7,114, I l

TABLE 4.313 EXPLOS!VE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH' CHANNEL SOURG CHANNEL FUNCTIONAL SURVEILLR4CE INSTRUMENT CHECK CHECK CAUBRATION TEST AEOUIRED

1. DELETED -

2. WASTEGAS HOLDUP SYSTEM EXPLOSIVE GASMONITORING SYSTEM

a. Hydrogen Monitor D

N.A. O(3) M

b. Oxygen Monitor D

N.A. O(4) M During process vent system operation (treatment for primary system offgases) { ( 3 ) The CHANNEL CAllBRATION shallinclude the use of standard gas samples containing a nominal: -1. One volume percent hydrogen, balance nitrogen, and

2. Four volume percent hydrogen, balance nitrogen.

( 4 ) The CHANNEL CAllBRATION shallinclude the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance narogen.

NORTH ANNA UNIT 2 3/4 3 54 Amendment No. 37,114, 1 ^ ^ " ^

4 i

Specifications 3/4.11.1.1 through 3/4.11.1.3 have been deleted.. NORTH ANNA UNIT 2 3/4 11 1 Amendment No. 37,$7,Il4,

RADCACTMESTORAGE L!OutD HOLDUP TANKS L!MITING CONDITION FOR OPERATION 3.11.1.4_ The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. L a. Refueling Water Storage Tank b. Casing Cooling Storage Tank c. PG Water Storage Tank' 1' d. Boron Recovery Test Tank'- e. Any Outside Temporary Tank" t i A PPLIC ABILITY: At all times. ACTION: With the quantity of radioactive materialin any of the above listed tanks exceecing a. p the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. t SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per week when radioactive materials are being added to the tank. ~Yhls Is"a ~sh5tebysteirIwiih ijnit I. ~ ~ " Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste ion exchanger system. NORTH ANNA UNIT 2 3/4 11 2 Amendment No. 37, I N ' l

3.: t j l l a i 1 i Specifications 3/4.11.2.1 ' through 3/4.11.2.4 have been deleted b NORTH ANNA UNIT 2 3/4 11 3 Amendment No. 37,114,

RADIOACTIVE STORAGE d 3/4.11.2 GAS STORAGE L i \\ EXPLOSlVE GAS MfXTUPE i 1 I LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas decay' tanks shall be limited to less than i or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume and is less than 96% by volume. APPLICABILITY: At all times. ACTION: I

a. With the. concentration of oxygen in the waste gas decay tanks greater than 2% by' volume but less than or equal to 4% by volume, reduce the oxygen concentration to the i

above limits within 48 hours.

b. With the concentration of oxygen in the waste gas decay tanks greater than 4% volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to'tess than or equal to 2% by volume without delay.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas decay tanks shall be determined to be within the above limits by continuously maitoring the waste gases in the waste gas decry tanks with the hydrogen and oxygen monitoa r. quired OPERABLE by Table 3.3-13 of Specification 3.3.3.11. 1 NORTH ANNA UNIT 2 3/4 11 4-Amendment No. & 114,

RADCACTIVE STORAGE o GAS STORAGE TAWS i .s LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of rPdioactivity contained in each gas' storage tank shall be limited to less than or equal to s 25,000 curies noble gases (considered as Xe 133). APPLICABILITY: At all times. ) ACTON:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per month when the specific activity of the primary reactor coolant is s 1.0 Cl/gm DOSE EQUIVALENT l 131, Under conditions which result in a specific activity > 1.0 Ci/gm DOSE EQUIVALENT l 131, the Gas Storage Tank (s) shall be sampled once per 24 hours, when radioactive materials are being added to ther tank. NORTH ANNA UNIT 2 3/4 11 5 Amendment No. 37,114

I l l l Specifications 3/4.11.3 through 3/4.11.4 have been deleted k I l l-NORTH ANNA UNIT 2 3/4 11 6 Amendment No. 37,114 i

i ( l t 1 Specifications 3/4,12,1 through 3/4.12.3 have been deleted 1 l-l l l 1 1 NORTH ANNA UNIT 2 3/4 12 1 Amendment No. U ;#7.1l4

i 4 r This Page Intentionally Left Blank t i i l NORTH ANNA UNIT 2 8 3/4 34 Amendment No. 37, Il4'

\\ t i Specifications 3/4.11.1.1' through 3/4.11.1.3 have been deleted i 1 { i l ( l NORTH ANNA UNIT 2 8 3/4 11 1 Amendment No. JJ,114

t. 1 RADICAOTIVE STORAGE 3/4.11.1 LIOUID STORAGE BASES 3/4.11.1.4 LIQUID WOLDUP TANKS The tanks listed in this Specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the nuantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be 'ess than the limits of 10 CFR Part 20, Appendix B, Table ll, Column 2, at the nearcat potable water supply and the nearest surface water supply in an UNRESTRICTED AREA. 1 Specifications 3/4.11.2.1 through 3/4.11.2.4 have been deleted. 4 NORTH ANNA. UNIT 2 B 3/4 11 2 Amendment No. 37,114,

= RADIOACTIVE STORAGE 3!4.11.2 GAS STORAGE EMSES l'4.112 5 EXPLOSIVE GAS MIXTURE This Specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. 3/4.11.2 6 GAS STORAGE TANKS The tanks included in this Specification are those tanks for which the quantity of ( radioactivil' contained is not limited directly or indirectly by another Technical Specification y to a quantity that is less than the quantity which provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an' uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. -This is consistent with Branch Technical Position ETSB 115 in NUREG 0800, July 1981. Specifications 3/4.11.3 and 3/4.11.4 have been deleted. I I NORTH ANNA - UNIT 2 8 3/4 11 3 Amendment No. 37.114,

\\ % !,g 9

)

t i 1 I l l l l 1 1 I l r 4 4 I i

Q i l, i Specifications 3/4.12.1 through 3/4.12.3 have been deleted i ) NORTH ANNA UNIT 2 8 3/4 12 1 Amendment No. p, 114, 1 s.,- -

ADMINISTRATIVE CONTROLS (. l b.- In-Plant Radiation Monitoring A program'which will ensure the capability to accurately det & ! S the airborne iodine concentration in vital areas under accident conditions.. This program shall include the following: (1) Training of personnel, l (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: (1) 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, (iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for all control point chemistry conditions, (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action; and (vii) ' Monitoring of the condensate at the discharge of the conden-i sate pumps for. evidence of condenser inleakage. When condenser in'-leakage is confirmed, the leak shall be repaired, plugged, or isolated within 96 hours. d. Post-Accident Sampling A program which will ensure the capability to-obtain and analyze' reactor coolant, radioactive iodines and particulates in plant i gaseous effluents, and containment atmosphere samples under - accident conditions. The program shall include the following: (i) Training of personnel, (ii) Procedures for sampling and analy' sis. (iii) Provisions for maintenance of sampling and analysis equip-ment. NORTH ANNA - UNIT 2 6-14a Amendment No. 50 t 0 g m-. - -. ~.. .,--[9

l 'J .,l ADMINISTRATlVE CONTRO(,S e. Radiatt*tive Etha91 Controit Prooram ig I \\ i A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable, ) The program.(1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) l shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: i L 1 ) Limitations on the operability-of: radioactive liquid and' gaseous monitoring j i instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,- J 2 ) Limitations 'on the concentrations of radioactive material released in liquid-- effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table 11. Column 2, j ' 3 ) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20,106 and with the methodology and parameters in the -

ODCM,

~' 4 ) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each ,. unit to UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50, 5 ) Determination of cumulative and projected dose contributions from radioactive affluents for the current calendar quarter and-current calendar-year in i accordance with the methodology and parameters in the ODCM at least every 31--

days,

( ( ~ 6 ) Limitations on the operability and use of the liquid and gaseous effluent treatment - systems to ensure that the appropriate portions-of these systems are used to reduce releases of radioactivity when the projected doses in-a 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7 ) Limitations on the dose ate resulting from radioactive material released in gaseous effluents to areas Doyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix 8. Table 11, Column 1 NORTH ANNA UNIT 2 6-14b AmendmentNo. f7,114 u

.6 g j ADMINISTRA3VE CONTROLS 6.8.4 e, Radienctive Effluent C ntref t Dreeram (Coh't ) 8) Limitations on the annual and Quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNARY l conforming to Appendix I to 10 CFR Part 50, 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from locine 131, lodine 133, tritium,- and all radionuclides in particulate form with half. lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix i to 10 CFR 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation' from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Andiolocical Environmental Monitorina Precram A program shall be provided _ to monitor the radiation and radionuclides in' the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of. the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the-CDCM, (2) conform to the guidance of Appendix 1 to 10 CFR Part 50, and (3) include the following: 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in acccidance with the methodology and parameters in the

OOCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3) Participation in a interlaboratory. Comparison Program to. ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. NORTH ANNA UNIT 2 6-14c Amendment No.ll 4,

.l ADMINISTRATIVE CONTROLS ~ 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regior.a1 Office of Inspection and Enforcement unless t otherwise noted. STARTUP REPORTS 6.9.1.1 A ' summary report of plant startup and power escalation testing shall be submitted following (a) receipt of an operating license. (2 amend-ment'to the license involving a planned increase in power level (3)) instal-lation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. 6 4 NORTH ANNA - UNIT 2 ~6-14d Amendment No.47 114 l

a ADMINISTRATIVE CONTROLS (Continued) - ANNUAL RADIOLOGICAL ENVIRONMsNTAL OPERATING REPORT' 6.9.1.8 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3,and IV.C of Appendix I to 10 CFR Part 50. 1 j .i i r A sin ~gIe submittal riiay~iEIda~o~e~for a multiple unit station. ~ NORTH ANNA UNIT 2 6 19 Amendment No. 37.47,64, 114,

.:l ADMINISTRATIVE CONTROLS (Continued) SEMIANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT *. 6.9.1. 9 The Semiannual Radioactive Effluent Release Report covering the operation of the unit' during the previous 6 months of operatiori shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Part 50. 1 1

A single submittal may be made for a multiple unit station.. The submittal should combine those sections that are common to all units at the stationt

) however, for dits with separate radwaste systems, the submittal shall' specify the releases of radioactive material from each unit. NORTH ANNA UNIT 2 6 20 Amendment No. 37,f 7,114,

I \\ ADMINISTRATIVE CONTROLS SDECIAL REDORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region ll, within the time period specified for each report. These reports shall be submitted pursuant to the requirement of the applicable specification:

a. Inservice inspection Reviews, Specification 4.0.5, shall be reported within 90 days of 4

completion. t

b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.

c. FIRE DETECTION INSTRUMENTATION. Specification 3.3.3.7.

d. RADIATION MONITORING INSTRUMENTATION Specification 3.3.3.1, TABLE 3.3 6 }' Action 35.

e. ' REACTOR COOT. ANT SYSTEM SPECIFIC ACTIVITY. Specification 3.4.8.

f. OVERPRESSURE PROTECTION SYSTEMS. Specification 3.4.9.3. g. EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3 { h. SETTLEMENT OF Ct. ASS 1 STRUCTURES. Specification 3.7.12.

i. GROUND WATER LEVEL. SERVICE WATER RESERVOIR. Specification 3.7.13.

j. FIRE SUPPRESSION SYSTEMS. Specification 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4.

3.7.14.5 and 3.7.14.6. k. PENETRATION FIRE BARRIERS. Specification 3.7.15, I. RADIOACTIVE EFFLUENTS. As required by the ODCM.

m. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM.

n. SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.

REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specification 4.4.10. For any o. abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during the performance of Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.

p. CONTAINMENT STRUCTURAL INTEGRITY. Specification 4.6.1.6 For any abnormal degradation of the containment structure detected during the performance of Specification 4.6.1.6, an initial report shall be submitted within 10 days after completion of Specification 4.6.1.6.

A final report which includes (1) a description of the condition of the liner plate and concrete, (2) inspection procedure, (3) the tolerance on cracking, and (4) the corrective actions taken, shall be submitted within 90 days after the completion of Specification 4.6.1.6. NORTH ANNA UNIT 2 6 21 Amendment No. 37,#7,$3, pp,114,

} -ADMIN!STRAT!VE CONTROLS-(Continued) 6.10 RECORD RETENTION In a' dition to the applicable record retentton requirements of Title 10, Code d of Federal Regulations, the following records shall be retained for at least the minimum' period indicated. 6.10.1 The' following records shall be retained for at least five years: Records-and-logs of facility operation covering time interval at a. each power level. 4 b, Records and logs'of principal maintenance activities, inspectinns, repair and replacement of principal items 'of equipment related to nuclear safety. c. All REPORTABLE EVENTS and Special Reports, d. Records of surveillance activities, inspections and calibrations. required by these_ Technical Specifications. 4 Records of changes made to Operating Procedures. e. a. f. Records of radioactive shipments. g. Records of sealed sourca leak tests,and results, h. Records of annual physical inventory of all sealed. source material of record. i. Records of the annual audit of the Station Emergency Plan and implementing procedures. 4 j. Records of the annual audit of-the Station Security Plan and implementing procedures. l 6.10.2 The following records'shall be retcined for'the duration of the Facility Operating License: i Records and drawing changes reflecting facility design modifications a. made to systems ~and equipment described in the Final Safety Analysis Report.. b. Records of new and irradiated fuel inventory, fuel transfers and. assembly burnup histories, Records of facility radiation end contamination surveys, c. d. Records of radiation exposure for all individuals entering radiation control areas, Records of gaseous and liquid radioactive material release to the e. environs. f. Records of transient or operat onal cycles for those facility 4 components identified in Table 5.7-1. ' NORTH ANNA - UNIT 2 6-22 Amendment No. 3J,A/ 67

ADMINISTRATIVE CONTROLS (Continued)- g. Records of reactor tests and experiments. ' h. Records of training and qualification for current members of the plant staff. 4 1. Re.urds of in service inspections performed pursuant to these Technical Specifications. i } J. Records of Quality Assurance activities required by the OA Manual. I i(. P.ecords of the service life of all hydraulic and mechanical snubbers required to be. 1 operable ey Technical Specification 3.7.10 including the date at which the service l life commences and associated installation and mi:enance records, l. Records of reviews performed for-changes made to procedures or equipment or reviews of tests and experiments parruant to 10 CFR 50.59. m. Records of meetings of the SNSOC. Records of meetings of the System Nuclear Safety and Operating Committee to n. i' issuance-of Amendment No.11. Records of secondary water sampling and water quality, o. p. Records for Environmental Qualification wh;cn are covered under the provisions of Paragraph 2.C(4) (3) of License Nc NPF.7. q. Records of analyses requitect by Qe radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date. This. would included procedures effective at specified times and QA records showing that these procedures were followed, Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION r. MANUAL and the PROCESS CONTROL PROGRAM. 6.11 AADIATION PAOTECTION PAOGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6 12 WIGH AADIATION AAEA j 6.12.1 in lieu of the " control device" or " alarm signal

required by paragraph 20,203(c) (2) of 10 CFR 20 each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted a high radiation area and entrance NORTH ANNA UNIT 2 6 23 Amendment No. 77.37.53,57,

114, h

sc/

i ADMINISTRATIVE CONTROLS (Contitrued) thereto shall be centrolled by requiring issuance of a Radiation Work Permit *. ~ u Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followings A radiation monitoring device which continuously indicates the ^ a. radiation dose rate in the area. b. A rtdiation monitoring device which continuously int 9 grates the radiation doge rate in the area and alarms vr.tn a pre. set integrated dose is received. Entry into such areas with this monitcring devi;e may be made after the dose rate level in the area hae been estaby.shed and personnel have been made knowledgeable of them. E An individual qualified in the protection procedures who is 3 quipped c. with a radiation dose rate monitoring device. This individual Oht!1 be responsible fer providing positive control over the activities within the area and shall perform. periodic radiation surveillance at p the frequency specified by the facility Health Physicist in the Radiation Work Permit. M-6.12.2 The requirements of 6.12.1, above, shall also apply to each high lhL radiation area in which the intensity of radiation is grea*er than.1000 mrem /nr. In addition, locked doors shall be provided to present unauthorized entry into such areas and the keys shall be maintained under the administra-tive control of the Shif t Supervisor on duty and/or the Plant Health Physicist.

Health Physics personnel or personnel escorted by. Health Physics personnel shall be exempt froa the RWP issuance requirement 'during the perfornance of s

I their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry in high radiation areas. NORTH ANNA - UNIT 2 6-24 Amendment No. 31 u..

t e r ADM!NISTRATIVE CONTROLS 6 13 DmOCESS CONTAOL DDCGRAM fDCP) g Changes to the PCP: a. Shall be documented and recorcs cf reviews performed shall be retained as required by Specification 6.10.2.r. This documentation shall contain: 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or othr l applicable regulations. b. Shall become effective after review and acceptance by the SNSOC and the approval of the Plant Manager. 6.14 OFC9lTE DO9E C ALCULATION M ANU AL rODCM) Changes to the CDCM: a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.r. This documentation shall contain: 1) Sufficient information to support the change togetner with the appropriate analyses or evaluations justifying the change (s) and 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dese, or setpoint calculations, b. Shall become effectrve after review and acceptance by the SNSOC and the approval of i the Plant Manager, c. Shall be submitted to the Commission in the form of a complete, legible cooy of the l entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected l pages, clearly indicating the area of the page that was changed, and shallindicate the l date (e.g., month / year) the change was implemented. l l NORTH ANNA UNIT 2 6*25 Amendment No. U,114,

~ a.,- y . y. = g', nl.l,7 , c = m,.c . r e.j, _g y J!.. 'l, 7 F. c,1 p ty 1. 5 '.. J 3 .-r. 3, .c-. y, i . e.. ma . - ~ , o e 4 1 g, s t .'g I 1 Y 1 .g m. ,m t

' \\

a-3 i .g ~ 4. I,, a t t } g = e-g' g' .-(- L y "I -{ 4 g , ;g I ( e, y 1 _ O, s s 'j 4. d ( .I I f. g

g. g i

u_ -:-n ~. t ; >I i le, s ) 't n.; a',. r . -s, t s ni: 4 1s'}_. 9 i s;p i ~' .1t -- ) !. =' { h 1.; 4 6-15 is DELETE 0'- fh '.. i 1 .'l i 2 - F; k i h.' i A t i b fy', i 13. ..' j ; i f v f a;}} NORTH ANNA -UNff 2 6 -'AmendmentL-No E

114, t

7 4 l r. 3 -s f _k l') l __ - { j I 5 2 .'\\-. ~l ,:f l' f _ Q, tn. 'T ( [ k 4 h, ( ^N'i

4 r

4 c,,c';.., e - 3 e g. g:.. a + 3 r i. <=t; 3 \\\\}}

ML20055H377

Text

Attachment:

Attachment:

Navigation menu

Search