ML19312C492
| ML19312C492 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/16/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C491 | List: |
| References | |
| NUDOCS 7912160048 | |
| Download: ML19312C492 (21) | |
Text
{{#Wiki_filter:_- UNITE 3 CTATES ^ ^ M1 NUC6.nAR RESULATORY COMMISSION CASHINGTON, D. C. 205516 j &*.s-!. I DUKE POWER COMPANY DOCKET NO. 50-269 OC0 HEE NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO OPERATING OPERATING LICENSE Amendment No. 41 License No. DPR-38 1. The Nuclear Regulatory Comt:.ission (the Commission) has found that: A. The application for amendment by Duke Power Company (the licensee) dated November 1,1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 1 ?912100Ogg>
2-2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. OPR-38 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 41, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective within 30 days after the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION H44 WIN - i,, A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 16,1977 l C A y,
f ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 41 TO DPR-38 AMENDMENT NO. 41 TO DPR-47 AMEN 0 MENT NO. 38 TO DPR-55 00CKETS NOS 50-269, 50-270 AND 50-287 Revise Appendix A as follows: Remove the following pages and insert revised identically numbered pages. 3.2-1 3.3-3 3.5-1 3.5-2 3.5-8 3.5-9 3.5-11 6.1-7 6.4-1 6.5-1 6.5-2 6.6-6 Table 4.11-3 Add the following new page. 3.2-la
' - ~ ~ ry BIGH PRF.SSURE INJECTION AND CHD(ICA2. ADDITION SYSTDiS 3.2 Agglicability Applies to the high pressure injection and the chemical addition systems. Objective To provide for adequate boration under all operating conditions to assure ability to bring the reactor to a cold shutdown condition. Specification The reactor shall not be critical unless the following conditions are met: Two high pressure injection pumps per unit are operable except as 3.2.1 specified in 3.3. One source per unit of concentrated soluble beric acid in addition 3.2.2 This to the borated water storage tank is available and operable. can be either: The boric acid mix tank containing at least the equivalent of a. 450 ft3 of 10,600 ppm boron as boric acid solution at c temperature of at least 10*F above the crystallization System piping and valves necessary to establish temperature. a flow path from the tank to the high pressure injection system shall also be operable and shall have at least the same One as-temperature requirement as the boric acid mix tank. sociated boric acid pump shall be operable. If the daily average air temperature in the vicinity of this tank and as-sociated flow path piping is less than 85'F, at least one channel. heat tracing shall be in operation for this tank and piping. b. The concentrated boric acid storage tank containing at least the equivalent of 550 ft3 of 8700 ppm boron as boric acid solution with a temperature of at least 10*F above the crystallization temperature. System piping and valves necessary to establish a flow path from the tank to the high pressure in-jection system shall be operable and shall have the same temperature requirement as the concentrated boric acid storage tank. One associated boric acid pump shall be operable. If the daily average air temperature in the vicinity of this tank is less than 70*F, at least one channel of heat tracing shall be in operation for this tank and associated piping. Transfer between the boric acid mix tank and the cencentrated boric acid storage tank is permitted, provided the contents of one tank the requirements specified above immediately pt Lar to and meet If neither source of concentrated soluble borie after transfer. the borated acid in Specification 3.2.2 a and b is available, but least one of these water storage tank is available and operable, at sources shall be restored to operability within 72 hours or the reactor shall be placed in a hot shutdown condition and be borated toashutdownmarginequivalentto1%4{at 200*F within the next if at least one source of concentrated boric acid has not 12 hours; 321 Amendments Nos. 41, 41 & 38 t
^ '} J been restored to operability within the next 7 days the reactor shall be placed in a cold shutdown condition within an additional 30 hours. one source of soluble boric acid as indicated by If at least the berated water storage Specification 3.2.2 a and b is available but tank shall be restored to that tank is neither available nor operable, operability within one hour or the reactor shall be placed in a hot shutdown condition within 6 hours and in a cold shutdown conditio within an additional 30 hours. j [ ) b l l 3.2-la Amendment Nos. 41, 41 & 38 l
3.3.6 Exrptionsto].5thc11b2csfrilows: ( (c) Both esro flooding tcnks sh0ll ba cperctienni ab;va 800 psig. (b) Both motor-operated valves associated with the core flooding tanks shall be fully open above 800 psig, (c) One pressure instrument channel and one level instrument channel e per core flood tank shall be operable above 800 psig. (d) One reactor building cooling f an and associated cooling unit shall be permitted to be out of service for seven days provided both rqactor building spray pumps and associated spray nozzle headers are in service at the same time. the If the requirements of Specification 3.3.l(f) are not met, borated water storage tank shall be considered unavailable and (e) action shall be initiated in accordance with Specification 3.2. Prior to initiating maintenance on any of the components, the dupli-shall be tested to assure operability. 3.3.7 cate (redundant) component Bases The requirements of Specificatian 3.3 assure that, before the reac9 r can Two be made critical, adequate engineered saf ety features are operable. high pressure injection pu=ps and two low pressure injection pumps are However, only one of each is necessary to supply emergency specified. Both coolant to the reactor in the event of a loss-of-coolant accident. core flooding tanks are required as a single core flood tank has insufficient inventory to reflood the core.(1) The borated water storage tanks are used for two purposes: (a) As a supply of borated water for accident conditions. (b) As a supply of borated water for flooding the fuel transf er canal during refueling operation.(2) gallons of borated water (a level Three-hundred and fifty thousand (350,000) in the BWST) are required to supply emergency core cooling and of 46 feet of a loss-of-core coo' ling accident. reactor building spray in the event The berated This amount fulfills requirements for e=ergency core cooling. 383,000 gallons is based on refueling volume water storage tank capacity of Heaters maintain the borated water supply at a temperature requirements. at the amount of boren freezing. The boron concentration is set 70"F without any to prevent required to maintain the core 1 percent suberitical atThis concentration is 1,33 control rods in the core. mini =um value specified in the tanks is 1,800 pps baron. The spray syste= utilizes co=en suction lines with the low pressure in-e If a single train of equipeent is remeved from either jection syste:. be assured to be operable in each systec. l I system, the other train must When the reactor is critical, maintenance is allowed per Specification 3.3.5 and 3.3.6 provided require =ents in Specificacica 3.3.7 are met which assure operability of the duplicate co:ponents. Operability of the specified com-i
- 3. b3 Amendment Nos. 41. 41 & 38
] 3.5 1NSTRUMENTAT10N SYSTDiS 3.5.1 Operational Saferv instrumentation Applicability Applies to unit instrumentation and control systems. Obiective To delineate the conditions of the unit instrumentation and safety circuits necessary to assure reactor safety. Specifications The reactor shall not be in a startup mode or in a critical state 3.5.1.1 unless the requirements of Table 3.5.1-1, Columns A and B are met. that the number of protective channels operable falls In the event 3.5.1.2 below the limit given under Table 3.5.1-1, Columns A and 5; operation shall be limited as apecified in Column C. For on-line testing or in the event of a protective instrument or 3.5.1.3 channel failure, a key-operated' channel bypass switch associated with each reactor protective channel may be used to lock the channel Status of the untripped state trip relay in the untripped state.Only one channel bypass key shall be shall be indicated by a light. accessible for use in the control room. Only one channel shall be locked in this untripped state or contain a dummy bistable at any one time. For on-line testing or maintenance during reactor power operation, 3.5.1.4 a key-operated shutdown bypass switch associated with each reactor protective channel my be used in conjunction with a key-operated channel bypass switch as limited by 3.5.1.3. Status of the shutdown bypass switch shall be indicated by a light. During startup when the intermediate range instruments come on scale, 3.5.1.5 the overlap between the intermediate range and the, source range instrumentation shall not be less than one decade. If the overlap is less than one decade, the flux level shall not be greater than that readable on the source range instruments until the one decade overlap is achieved. 3.5.1.6 In the event that one of the trip devices in either of the sources supplying power to the control rod drive mechanisms fails in the untripped state, the power supplied to the rod drive mechanisms through the failed trip device shall be manually removed within 30 The condition will be corrected and the remaining trip minutes. devices shall be tested within eight hours. If the condition is not corrected and the remaining trip devices tested within the eight hour period, the reactor shall be placed in the hot shutdown condition within an additional fotr hours. i l Amendment Nos. 41, 41 & 38 ( 3.5-1 l
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\\ D "" *" D o o JL o _a Bases Every reasonable effort will be made to maintain all safety instrumentation in A startup is not permitted unless three power range neutron instru-four reactor operation. channels and two channels each of the following are operable: temperature instrument channels, four reactor coolant flow instrument ment coolant channels, four pressure-channels, four reactor coolant pressure instrument temperature instrument channels, four flux-imbalance flow instrument channels, channels, and high reactor building four power-number of pumps instrument pressure instrument channels. The engineered safety faatures actuation system must have two analog channels functioning correctly prior to n startup. least Operation at rated power is permitted as long as the systems have at This is in the redundancy requirements of Column B (Table 3.5.1-1). agreement with redundancy and single failure criteria of IEEE 279 as described in FSAR Section 7. A fifth channel that is isolated There are four reactor protective channels. from the reactor protective system is provided as a part of the reactor Normal trip logic is two out of four. Required trip logic control system. Minimum for the power range instrumentation channels is two out of three. trip logic on other channels is one out of two. The four reactor protective channels were provided with key operated bypass switches to allow on-line testing or maintenance on only one channel at a Each channel is provided alarm and lights to time during power operation. There will be one reactor protective indicate when that channel is bypassed. That key will be system bypass switch key permitted in the control room. under the administrative control of the Shift Supervisor. Spare keys will be maintained in a locked storage accessible only to the station Manager. ~ Each reactor protective channel key operated shutdown bypass switch is provided with alarm and lights to indicate when the shutdown bypass switch There are four shutdown bypass keys in the control room under is being used. the administrative control of the Shift Supervisor. The use of a key operated shutdown bypass switch for en-line testing or maintenance durine resctor power operation has no significance when used in conjunction with a key operated channel bypass switch since the channel trip relay is locked in the untripped The use of a key operated shutdown bypass switch alone during power When the shutdown bypass switch is state. operation will cause the channel to trip. operated for on-line testing or maintenance during reactor power operation, reactor power and RCS pressure Ifmits as specified in Tahle 2.3-1A. B. or C are not applicable. The source range and intornodiste range nuclear instrumentation overlap by one10-10 amps n decade of neutron flux. This decade overlap will he achieved at the intermediarc ranoe instrument. I Power is normally supplimi to t he cont rol rod drive mechani m from two .woorrew. Nclundant t rip device, are employed in separate paralle! 600 voltI f any one of t hese t rip devices f all:, in the untripped ec h of these sonree.. state on-line repairs to thc failed deelee, when practical, will be made, and the remaining trip devices will be tested. Four hours is ample time to test the remaining trip devices and in many cases make en-1:ne repairs. REFERENCE FSAR,-Section 7.1-Amendment Nos. 41, 41 & 38 i 3.5-2
)vidtdincpoeificatfun3.5.2.4.'}thereretor (3) Exc2pt es chall be brought to.the hst shutdown condit1w.s within fcur hours if ths quadrant powar tilt is not reduc,ed to 1 css than 3.41% Unit I within 24 hours. i 3.41% Unit 2 4.92% Unit 3 efit exceeds +3.41 Unit 1 and there is simultaneous .b. If the quadrant 3.41% Unit 2 4.92% Unit 3 indication of a misaligned control rod per Specification 3.5.2.2, reactor operation may continue provided power is reduced to 607. of the thermal power allowabic for the reactor. coolant pump combination. if quadrant tilt exceeds 9.44% Unit 1 Except for physics test, 9.44% Unit 2 c. 11.07% Unit'3 a controlled shutdown shall be initiated immediately, and the reactor shall be brought to the hot shutdown condition within four hours. Whenever the reactor is brought to hot shutdown pursuant to d. 3.5.2.4.a(3) or 3.5.2.4.c above, subsequent reactor operation testing, and is permitted for the purpose of measurement, corrective action provided the thermal power and the power range high flux setpoint allowable for the rea: tor coolant pucp combination,are restricted by a reduction of 2 percent of full power for each 1 percent tilt for the maximum tilt observed prior to shutdown. Quadrant power tilt shall be moni:ored on a minimum frequency of once every two hours during pouer operation above 15 percent e. of rated power. 3.5.2.5 ' Control Rod Positions Technical Specification 3.1.3.5 does not prohibit.the exercising of iddividual safety rods as requi7ed by Table 4.'l-2 or apply to a. inoperable safety rod limits in Technical Specification 3.5.2.2. Except for physics' tests, operating rod group overlap shall be If this limit is exceeded. b. 25% 15% between two sequential groups. corrective measures sh Acceptable overlap shall be attained within two table overlap. hours, or the reactor shall be placed in a hot shutdown condition within an additional 12 hours. Except for physics ' tests or exercising control rods, the control e specified on Figures 3.5.2-13.' and c. rod withdrawal limits ar, 3.5.2-1A2, (Unit 1), 3.5.2-1B1, 3.5.2-1112 and 3.5.2-1B3 (Unit 2), and 3.5.2-1C1, 3.5.2-1C2, and 3.5.2-1C3 (Unit 3) for four pump 1), 3.5.2-2n), operation and on Figures 3.5.2-2A1, 3.5.2-2A2 (Unit I 3.5.2-232, 3.5.2-2n3 (Unit 2), and 3.5.2-2C (Unit 3) for three oc i \\ 3.5-8 Amendment Nos. 41, 41 & 38. l l
' limits cro ,x If the central rod po2itic twa pump opar..fcn. cxeccd:d, corr:ctivo me:surcs chall ba taken immediccoly toAccGptcblo centro' achieve an accepet.blo esntrol rod po31ticn. The rod position shall then be attained within two hours. h ll minimum shutdown margin required by Specification 3.5.2.1 s a be maintained at all times. be increased above the physics tests, power shall Pot power level cutoff as shown on Figures 3.5.2-1A1, 3.5 Except fot d. (Unit 1), 3), unless the following 3.5.2-1C1, 3.5.2-1C2, 3.5.2-1C3 (Unit requirements are met. of the value The xenon reactivity shall be within 10 percent (1) steady-state rated power. for operation at The xenon teactivity worth has passed its final maximum or l for minimum peak during its approach to its equilibrium va ue (2) the power level cutoff. operation at 3.5.2.6 Reactor power imbalance shall be monitored on a f requency not to raced power. exceed two hours during power operation above 40 per 2 3B1, 3.5.2-3B2, envelope defined by Figures 3.5.2-3A1, 3.5.2-3A2, 3.5. -If the imb Except defined by Figure 3.5.2-3A1, 3.5.2-3A2, 3.5.2-3B1, 3.5.2-382, 3.5.2 3.5.2-333, and 3.5.2-3C. and 3.5.2-3C, corrective measures shall be taken to achieve an achieved If an acceptable imbalance is not l limits acceptable imbalance. within two hours, reactor power shall be reduced until imba ance are met. all times with 3.5.2.7 The control rod drive patch panels shall be locked atto be aut ~ d alter-limited accese, nate. 3.5-9 Amendment Nos. 41, 41 & 38
^ 3 J / Control rod groups are withdrawn in sequence beginning with Group 1. Groups 5; 6, and 7 are overlapped 25 percent. The normal position at power is for Groups 6 and 7 to be partially inserted. i The quadrant power tilt limits set forth in Specification 3.5.2.4 have been cstablished with consideration of potential eff ects of rod bowing (Units 1 and j 2 only) and fuel densification to prevent the linear heat rate peaking increase associated with a positive quadrant power tilt during nor a1 power operation from exceeding 5.10% for Unit 1. The limits shown in Specif4. cation 3.5.2.4 5.10% f or Unit 2 l 7.36'; for Unit 3 cre measurement systen independent. The actua1 operating limits, with the cppropriate allowance for observability and instru=entation errors, for each systen are defined in the station operating procedures. measurenent ~ The quadrant tilt and axial i= balance =onitoring in Specification 3.5.2.4 I cod 3.5.2.6, respectively, normally will be performed in the process computer. The two-hour frequency for monitoring these quantities will provide adequate surveillance when the cc=puter is out of service. Allowance is provided for withdraval limits and reactor power imbalance limits to be exceeded for a period of two hours withour specification violation. Acceptable rod positions and imbalance must be achieved within the two-hour time period or appropriate action such as a reduction of power taken. Operating restrictions are included in Technical Specification 3.5.2.5d j to prevent excessive pcwer peaking by transient xenon. The xenon reactivity must be beyond its final maxim = or minimun peak and approaching its equilibrium value at the power level cutoff. REFERENCES D**]D *D ~3~l A b 4 FSAR, Sectica 3.2.2.1.2 W c Ju o 2FSAR, Section 14.2.2.2 1 1 C.'.2., S'."r ? ' ?.'!I:'T 9 B6** FUEL DENSIFICA2!0N R.:P' RT B A'?- 1409 (UNIT 1) B A*.4-13 9 6 (UNIT 2) I BA*!-1.00 (UNI. 3) 3.5-11 Amendment Nos. 41, 41.& 38 l-
Manager Oconee Nuclear Station I Maintenance Technical Services Operating Superintendent Superintendent Superintendent SRO Mechanical f' Performance Operating Maintenance Y Engineer Engineer SRO Engineer i Instrument and Shift Site llealth Electrical Supervisors g Physicist FR0 Engineer g 3 E 1 Shift Chemist w personneI a e-OCONEE NUCl EAR STATION eenie ma STATION ORGANIZATION DIART Ficune 6.1-1
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m i STATION OPERATING PROCEDURES 6.4 Specification The station shall be operated and maintained in accordance with Written prueedures with appropriate l 6.4.1 approved procedures. check-off lists and instructions shall be provided for the folleving conditions: Normal startup, operation and shutdown of the complete facility and of all systems and components involving nuclear a. safety of the facility, b. Refueling operations. specific and foreseen potential Actions taken to correct malfunctions of systems or components involving nuclear c. safety and radiation levels, including responses to alarms, suspected primary system leaks and abnormal reactivity changes. Emergency procedures involving potential or actual release d. of radioactivity, Preventive or corrective maintenance which could affect e. nuclear safety or radiation exposure to personnel. f. Station survey following an earthquake. Radiation control procedures. g. h. Operation of radioactive waste management systems. Control of pH in recirculated coolant after loss-of-coolant 1. Procedure shall state that pH will be measured and the accident. addition of appropriate caustic to coolant will commence within 30 minutes after switchover to recirculation mode of core cooling to adjust the pH to a range of 7.0 to 8.0 within 24 hours. Nuclear safety-related periodic test procedures. J. Procedures shall in-Long-term emergency core cooling systems. k. clude provision for remote or local operation of system components necessary to establish low pressure injection within 15 minutes after a line break. Quarterly selected drills shall be conducted on site emergency 6.4.2 procedures including assembly preparatory to evacuation off site and a check of the adequacy of communications with off-site l l support groups. A respiratory protective program approved by the Commission shall be 6.4.3 in force. L l i 6.4-1 Amendment Nos. 41, 41 & 38 t
[. 9 6.5 STATION OPERATING RECORDS Specification The following records shall be prepared and permanently retained in a 6.5.1 manner convenient for review: Records of modifications to the station as described in the FSAR. a. Special nuclear material physical inventory records. b. Special nuclear material isotopic inventory records. c. Radiation monitoring records, including records of radiation and d. contamination surveys. Records of off-site environmental surveys. e. Personnel radiation exposure records as required by 10CFR20. f. Records of radioactive releases and waste disposal. g. Records of reactor coolant system in-service inspections. h.
- i. Preoperational testing records.
- j. Records of special reactor tests or experiments.
Records of changes to safety-related operating procedures. k. The following records shall be prepared and retained for a minimum of 6.5.2 six (6) years in a manner convenient for review: Switchboard Record. a. b. Reactor Operations Logbook. Shift Supervisor Logbook. c. d. Maintenance histories for station safety-related structures, systems and components. Records of safety-related inspections, other than reactor coolant e. system in-service inspections. f. Records of reportable occurrences. l'eriodic testinn records and records of other periodic checks, calibrations, etc. performed in accordance with surveillance g. I structures, systems requirements for safety-related narameters, and components. Amendment Nos. 41, 41 & 38 6.5-1
v. r' By-prcduct material invantory records, h. Minutes of Nuclear Safety Review Board meetings. i.
- j. Training records.
Test results, in units of microcuries, for leak tests pavformed k. pursuant'to Specification 4.16. i i l-t ~ 6.5 Amendment Nos. 41, 41- & 38 f ,p N.
f ^ s b. Thirty-Day Written R ports The types of events listed below shall be the subject of written reports to the Director, Office of Inspection and Enforcement, Region II, within 30 days of discovery.f the event. (Copy to the Director, Office of Management Informatics and Program Control) (1) Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established the by the technical specifications but which do not prevent fulfillment of the functional requirements of affected systems. (2) Conditions leading to operation in a degraded mode permit ted by a limiting condition for operation or shutdown required by a lims.Ing condition for operation. (3) Observed inadequacies in the implementation of administrati.ve or procedural controls during operation of a unit which could cause reduction of degree of redundancy provided in the Reactor Protective System or Engineered Safety Feature Systems. 6.6.2.2 Envivanmental Monitoring If individual milk samples show I-131 concentrations of 10 picoeuries per a. liter or greater, a plan shall be submitted within one week advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective of 15 mrem /yr to the thyroid of any indi- } vid ual. b. If milk samples collected over a calendar quarter show average concentrations of 4.8 picoeuries per liter or greater, a plan shall be submitted within 30 days advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective of 15 mrem /yr to the thyroid of any individual. c. If, during any annual report
- period, a measured level of radioactivity in any environmental medium other than those associated with gaseous radiciodine releases or liquid effluent releases exceeds ten times the the control station value, a written notification will he submitted within one week advising the NRC of this condition. This notification should include an evaluation of any release ennditions, environmental factors, or other aspects necessary to explain the anomalous result.
d. If, during any annual report period, a measured level of radioactivity in any environmental medium associated with liquid effluent releases exceeds fif ty times' the control station value for sampling points ~ ~ at or upstream of location 000.7 or ten times the control station value for sampling points downstream of location 000.7, a written notification will be submitted within one week advising the NRC of this condition. This notification should include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result. l 1 Amendment.Nos.fl,41&38 6-6 9 4
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.1 i ..l ,i e i i i ,- pn !.1 l r. -a. , r:~ . b.1"1 i i li i.] q.1.1.i I f '. I l ld Et b'::l.l.IL3 "qi -: r c: 2 x.r. ri ii u;...-.: 't !! lIn L1J L1LT_1.U; 4 2 i h j p Amendment Nos. 41, 41 & 38
UNITE 3 STATES ^ c a Si NUCLEAR RE2ULATO3Y COMMISSION f j CASHINGTON, D. C. 20566 'M s 9....,$ '4 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO OPERATING OPERATING LICENSE Amendment No. 41 License No. OPR-47 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amencment by Duke Power Company (the ifcensee) dated November 1,1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There'is reasonable assurance (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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense ard security or to the health and ' safety of the public; and E. The issuance of thic amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. l
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-47 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.41, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective within 30 days after the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION /[uvWWt-A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 16, 1977 A
UNITE 3 STATES M JS NUCLEAR REIULATORY COMMISSION p-CASHINGTON, D. C. 20666 o L I .f p DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMEN 0 MENT TO OPERATING OPERATING LICENSE Amendment No. 38 License No. DPR-55 1. Tne Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Duke Power Company (the licensee) A. dated November 1,1976, complies with the standards and requirerpents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
~' . 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-55 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.38, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective within 30 days after the date of issuance. FOR THE NUCLLAR REGULATORY COMMISSION jkl<&MD A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 16, 1977 _}}