ML20052G849
| ML20052G849 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/06/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052G850 | List: |
| References | |
| NUDOCS 8205190067 | |
| Download: ML20052G849 (9) | |
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4 UNITED STATES E'
N NUCLEAR REGULATORY COMMISSION
,E WASHINGTON, D. C. 20555
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ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 30 l
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. License No. NPF-6 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power end Light Company (the licensee) dated June 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regclations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be 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
.,a-requirements have been satisfied.
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8205190067 820506 PDR ADOCK 05000368 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; by revising paragraph 2.C.(2) and by adding Paragraph 2.C.(3)(p) to Facility Operating License No. NPF-6 to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 30, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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2.C.(3)(p) Secondary Water Chemistry Monitoring
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The licensee shall implement a. secondary water chemistry l
monitoring program using the overall plant administrative procedure " Steam Generator Water Chemistry Monitoring, Unit II", to minimize steam generator tube degradation.
The program shall be defined in specific plant procedures and shall include:
1.
Identification of sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to measure the values of the critical parameters; 3.
Identification of process sampling points; 4.
Procedure for the recording and management of dat'a; 5.
Procedures defining corrective actions for off control point chemistry conditions; and 6.
A procedure identifying the authority responsible for the interpretation o,f the data, and the sequence and timing of administrative events required to initiate corrective action.
3.
This license amendment is effective within 30 days of the date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION
'T Q pfhSA Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes *to the Technical Specifdcations Date of Issuance:
May 6, 1982
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ATTACHMENT TO LICENSE AMENDMENT NO. 30 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368
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Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vert.ical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pages Insert Pages VII VII 3/4 7-11 3/4 7-11/12/13 3/4 7-12 3/4 7-13 8 3/4 7-3 B 3/4 7-3 4
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4. 7.1 TURBINE CYCLE Safety Va1ves...................................l....
3/4 7-1 E'ergency Feedwater System...........................
3/4 7-5 m
Condensate Storage Tank..............................
3/4 7-7 Act'ivity............................................
3/4 7-8 Main Steam Isolation Valves.........................
3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.....
3/4 7-14 3/4.7.3 SERVICE WATER SYSTEM.................................
3/4 7-15 3/4.7.4 EMERGENCY COOLING P0ND...............................
3/4 7-16 3/4.7.5 FLOOD PROTECTION.....................................
3/4 7-16a 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING AND AIR FILTRATION SYSTEM..................................
3/4 7-17 3/4.7.8 HYDRAULIC SHOCK SUPPRESSORS..........................
3/4 7-22 3/4.7.9 SEALED SOURCE CONTAMINATION..........................
3/4 7-27 3.4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................
3/4 7-29 Spray and/or Sprinkler Systems.......................
3/4 7-33
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Fire Hose Stations...................................
3/4 7-35 rr 3/4. 7-11 PENETRAT-ION FIRE BARR I ERS............................
3/4 7-37 l
3/4.7.12 SPENT FUEL P0OL STRUCTURAL INTEGRITY.................
3/4 7-38 3/4.8 ELECTRICAL POWER SYSTB4S I
3/4.8.1 A.C. SOURCES 0perating.............................................
3/4 8-1 Shutdown..............................................
3/4 8-5 l
l ARKANSAS - UNIT 2 VII Amendment No. 30 i
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INDEX t
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS '
i SECTION PAGE 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Di stri buti on - Operati ng........................ 3/4J8-6 A.C. Distribution - Shutdown.........................
'3/4 8-7 D.C. Di stribution - Operating........................ 3/4 8-8 D.C. Distribution - Shutdown.........................
3/4 8-10 Containment Penetration Conductor Overcurrent Pro tecti on Devices................................. 3/4 8 11 3/4.9 REFUELING OPERATIONS 3/4.9.1 B ORON CONCENT RAT ION.................................. 3/49-1 3/4.9.2 I NSTRUM ENTAT I ON...................................... 3/4 9-2 3/4.9.3 DECAY TIME...........................................
3/4 9-3, 3/4.9 4 CONTAINMENT BUILDING PENETRATIONS.................... 3/4 9-4 3/4.9.5 COMMUNICATIONS.......................................
3/4 9-6 3/4.9.6 REFUELING MACHINE OPERABILITY........................ 3/49-7 3/4.9.7 CRANE TRAVEL - SPENT FUEL POOL BUILDING.............. 3/4 9-8 3/4.9.8 COOLANT CIRCULATION,.................................
3/4 9-9 3/4.9.9.
WATER LEVEL - REACTOR V ESS EL......................... 3/4 9-10 3/4.9.10 SPENT FUEL POOL WATER LEV EL.......................... 3/4 9-11 3/4.9.11 FUEL. HANDLING AREA VENTILATION SYSTEM................
3/4 9-12
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3/4.10 SPECIAL TEST EXCEPTIONS
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3/4.10.1 SHUTDOWN MARGIN......................................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.............................................
3/4 10-2 3/4.10.3 REACTOR COOLANT L00PS................................
3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT..............................
3/4 10-4 3/4.10.5 MINIMUM TEMPERATURE FOR CRITICALITY..................
3/4 10-5 ARKANSAS - UNIT 2
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.These pages intentionally left i
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PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2.1 The temperatures of both the primary and secondary coolants in the steam generators shall be > 90 F when the pressure of either cool-ant in the steam generator is >275 psig.
APPLICABILITY: At all times.
ACTION:
With the requirements of the above specification not satisfied:
a.
Reduce the steam generator pressure of the applicable side to 1 275 psig within 30 minutes, and b.
Per. form an engineering evaluation to determine the effect of the overpressurization on tne structural integrity of the steam generator. Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200 F.
SURVEILLANCE REQUIREMENTS 4.7.2.1 The pressure in each side of the steam generators shall be determined to be < 275 psig at least once per hour when the temperature of either the primary or secondary coolant is < 90 F.
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_7 ARKANSAS - UNIT 2 3/4 7-14
i PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line and a.
ccncurrent loss of offsite electrical power. These values are consistent with the assumptions used in the accident analyses.
3/4. 7.1. 5 MAIN STEAM ISOLATION VALVES The OPERABILITY of the main steam isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise withir containment in the event the steam line rupture occurs within contain-ment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
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ARKAdSAS - UNIT 2 B 3/4 7-3 Amendment No. 30 l
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PLANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION
' The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed 1
.the maximum allowable fracture toughness stress limits. The limitations to 90 F and 275 psig are based on a steam generator RT f 30*F and NDT are sufficient to prevent brittle fracture.
3/4.7.3 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 EMERGENCY COOLING POND The limitations on the emergency cooling pond level and temperature ensure that sufficient coo. ling capacity is available to either 1) provide normal cooldown of the. facility, or 2) to mitigate the effects of acci-dent conditions within acceptable limits.
The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equip-ment without exceeding their design basis temperature and is consistent with the recomendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974.
3/4.7.5 FLOOD PROTECTION
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The limitation on flood protection ensures that facility protective f
actions wil'1 be taken in the event of flood conditions.
3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING / AIR FILTRATION SYSTEM The OPERABILITY of the control room emergency air conditioning / air filtration system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and ARKANSAS - UNIT 2 3 3/4 7-4
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