ML20134P205

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Amends 67 & 53 to Licenses NPF-4 & NPF-7,respectively, Correcting Discrepancies Re Radiological Effluent Tech Specs for Gaseous Waste Sampling & Analysis Program
ML20134P205
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 08/29/1985
From: Butcher E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20134P209 List:
References
NUDOCS 8509060193
Download: ML20134P205 (20)
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Text

{{#Wiki_filter:#[ g UNITED STATES de g NUCLEAR REGULATORY COMMISSION l WASHINGTON, D. C. 20555 r. 1 o, a %,...../ 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.67 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., (the licensee) dated September 28, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the 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. 8509060193 850829 PDR ADOCK 05000338 P PDR l

I t 5 i 2. Accordingly, the license is amended by changes to the Technical Soect-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. 67, 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 its issuance. FOR THE NUCLEAR REGULATORY COMMISSION 6LS Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 29, 1985 l i k .-e

.M as-2 a 1 I i ATTACHMENT TO LICENSE AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE 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 3/4 11-10 3/4 11-16 1 5-2 5-3 4 4 3

5 TABLE 4.11-2 4 ~ RADIDACTIVE CASE 00S WASTE SAMPLING AND ANAL.YSIS PROGRAM b$y Minimum Lower Limit of, 2 Sampling Analysis Type of Detection (LLD) H Caseous Release Type Frequency Frequency Activity Analysis (uci/ml) P P -0 A. Waste Cas Storage Each Tank Each Tank Principal Camma Emitters lx10 Tank Crab Sample B. Containment PURGE Each PURCE Each PURCE Principal Camma Emitters 1x10~ Crab -6 Sample H-3 lx10 h C C C. Process Vent M' M Principal Camma Emitters lx10~ Vent. Vent A Crah 2 7 Vent. Vent B Sample o -6 H-3 1x10 -12 D. All Release Types Continuous W' I-131 1x10 as listed in A, B, Charcoal C above. Sample f Continuous W' Principal Camma Emitters 1x10~ c Particulate Sample ~II Continuous M Cross Alpha 1x10 4 z Composite f Particulate Sample u Continuous Q Sr-89, Sr-90 1x10"II Composite Particulate Sample Continuous Noble Gas Noble Cases 1x10-Monitor Cross Beta or Camma

-1 TAllI.E 4.11-2 (Continued) 5 i g:n RADIOACTIVE CASE 0tlS WASTE SAMPLING AND ANALYSIS PROGRAM r h I Minimum Lower Limit of gy Sampling Analysis Type of Detection (LLD)* j Caseous Release Type Frequency Frequency Activity Analysis (uC1/ml) y i E W W Principle Camma Emitters lx10~ E. Condynser Air Ejector Vent Crab Sample -6 H-3 lx10 Steam Cencratpr Blowdown Vent i b -4 ) F. Containment Vacuum P P Principle Casuna Emitters lx10 t> Steam Ejector (flogger) Crab yy Sampl -6 H-3 lx10 ra O a it a F O 6

i 8 F RADIOACTIVE EFFLUENTS CASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The CASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation over 31 days. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous vaste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.3 urem to the critical organ

  • over 31 days.

APPLICABILITY: At all times. l ACTION: With gaseous vaste being discharged without treatment and in excess a. of the above limits, in lieu of a Licensee Event Report, prepare j and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that includes the following information: l. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or sub-systems, and the reason for the inoperability, 2. ACTION (s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of ACTION (s) taken to prevent a recurrence. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.

  • The critical organ is addressed in the ODCM.

NORTH ANNA - UNIT 1 3/4 11-15 Amendment No. 48

RADIOACTIVE EFFLUENTS EXPLOSIVE CAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the vaste gas decay tanks shall be limited to less than 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: 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 above limits within 48

hours, b.

With the concentration of oxygen in the vaste 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 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. SURVEILLANCE REOUIREMENTS 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 vaste gases in the vaste gas decay tanks with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-14 of Specification 3.3.3.11. NORTH ANNA - UNIT 1 3/4 11-16 Amendment No. M/,67

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/ UNITED STATES y p, NUCLEAR REGULATORY COMMISSION j WASHINGTON D. C. 20555 %,...../ 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. 53 License No. NPF-7 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated September 28, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the 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.

i . 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. 53, 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 its issuance. FOR THE NUCLEAR REGULATORY COMMISSION ~ Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 29, 1985

l ATTACHMENT TO LICENSE AMENDMENT NO. 53 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 4 amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to naintain document completeness. Page 3/4 11-10 5-1 5-2 5-3 6-23 i i t I

TABLE 4.11-2 3 ~ ?i* RADI0 ACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM E> Lower I.imit of Minimum h' Sampling Analysis Type of Detection (LLD)# "i Caseous Release Type Frequency Frequency Activity Analysis (uCi/ml) P P b -0 A. Waste Cas Storage Each Tank Each Tank Principal Camma Emitters lx10 Tank Crab Sample P P b 4 B. Containment PURCE Each PIIRGE Each PURCE Principal Camma Emitters Ix10 Crab -6 Sample 11 - 3 lx10 C. Process Vent M g Principal Camma Emitters lx10~ c c h Vent. Vent A Crab r. 7 Vent. Vent B Sample o -6 H-3 1x10 -12 D. All Release Types Continuous W" I-131 lx10 as listed in A, B, Charcoal C above. Sample Continuous W Principal Camma Emitters 1x10~ f Particulate py Sample N Continuous M Gross Alpha lx10~ n Composite 2 Particulate ,0 Sample -11 d Continuous Q St-89, Sr-90 lx10 wa Composite Particulate Sample Continuous Noble cas Noble Cases 1x10~ Monitor Cross Beta or Camma

i TABLE 4.11-2 (Continued) l 5 RADI0 ACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM so h Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)* c: i 35 Caseous Release Type Frequency Frequency Activity Analysis (uC1/ml) H l N E ~ W W Principle Gamma Emitters 1x10 E. Condynser Air Ejector Vent Crab i Sample -6 11 - 3 lx10 Steam Generatpr Blowdown Vent -4 af F. Containment Vacuum P P Principle Gamma Emitters lx10 Steam Ejector (llogger) Grab C Sample -6 H-3 1x10 o lI li a E J a e

_ = - _ = - -. s t 5.0 DESIGN FEATURES i 4 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1. LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2. l MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS i 5.1.3 Information regarding radioactive gaseous and liquid effluents, which allows identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MIMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-1. 5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape with a done roof and having the following design features: a. Nominal inside diameter = 126 feet. b. Nominal inside height = 190 feet, 7 inches. c. Minimum thickness of concrete walls = 4.5 feet. 4 d. Minimum thickness of concrete roof = 2.5 feet. e. Minimum thickness of concrete floor pad = 10 feet. f. Nominal thickness of the cylindrial portion of the steel liner = 3/8 inches. 0 g. Net free volume = 1.825 x 10 cubic feet. h. Nominal thickness of hemispherical done portion of the steel liner = 1/2 inch. DESIGN PRESSURE AND TEMPERATURE 5.2.2. The reactor containment building is designed and shall be maintained i for a asximum internal pressure of 45 psig and a temperature of 280*F. I l NORTH ANNA - UNIT 2 5-1 AmendmentNo.(N.53 r- .,,,.,7..

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.A, s. t i M M ANNA.ta n g 5-3 Amendment No. 3y,53 L

s j DESIGN FEATURES A l 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4. Each fuel rod shall 1 have a nominal active fuel length of 144 inches and contain a maxir.um total weight of 1780 grams uranium. The initial core loading shall have a maximum 1 enrichment of 3.2 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrich-ment of 4.1 weight percent U-235. l CONTROL R0D ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length control rod assemblies. i The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent 3 silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing. 5.4 REACTOR COOLANT SYSTEti DESIGN PRESSURE AND TEMPERATURE i j 5.4.1 The reactor coolant system is designed and shall be maintained: } a. In accordance with the code requirements specified in Section j 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, i b. For a pressure of 2485 psig, and c. For a temperature of 650*F, except for the pressurizer which is 680*F. VOLUME l 5.4.2 The total water and steam volume of the reactor coolant system is 9957 + 10 cubic feet at a nominal T,yg of 525 F. l NORTH ANNA - UNIT 2 5-4 Amendment No. 8,16

e 4 ADMINISTRATIVE CONTROLS (Continued) i g. Records of reactor tests and experiments. I h. Records of training and qualification for current members of the plant staff. i 1. Records of in-service inspections performed pursuant to these Technical Specifications. J. Records of Quality Assurance activities required by the QA Manual. i k. Records of the service life of all hydraulic and mechanical snubbers listed in Tables 3. 7-4a and 3.7-4b including the date at which the I service life commences and associated installation and maintenance records. 1. Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59. 4 m. Records of meetings of the SNSOC. i n. Records of meetings of the System Nuclear Safety and Operating Committee to issuance of Amendment No. 11. l J o. Records of secondary water sampling and water quality. p. Records for Environmental Qualification which are covered under the provisions of Paragraph 2.C(4)(e) of License No. NPF-7. q. Records of analyses required by the radiological environmental monitor-ing 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. 6.11 RADIATION PROTECTION PROGRAM 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 HIGH RADIATION AREA i 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 as a high radiation area and entrance NORTH ANNA - UNIT 2 6-23 Amendment No. II,/y),53 I (

s ADMINISTRATIVE CONTROLS (Continued) q thereto shall be controlled by requiring 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: a. A radiation monitoring device which continuously indicates the radiation dosa rate in the area. i i b. A radiation monitoring device which continuously integrates the j radiation dose rate in the area and alarms when a preset integrated i dose is received. Entry into such areas with this monitoring device aay be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them. c. An individual qualified in the protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall ] be responsible for providing positive control over the activities i within the area and shall perform periodic radiation surveillance 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 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administra-I tive control of the Shift Supervisor on duty and/or the Plant Health Physicist. l l l A .i-i

  • Health Physics personnel or personnel escorted by Health Physics personnel i

shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved I l radiation protection procedures for entry in high radiation areas. NORTH ANNA - UNIT 2 6-24 Amendment No. 31 ,m-..--.. .mr. -}}

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