ML20134P929

Amend 66 to License DPR-61,modifying Tech Specs to Add post- Accident Instrumentation Headings & New Limiting Conditions of Operation & Surveillance Requirements for post-accident Instrumentation

ML20134P929
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/03/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20134P922	List: ML20134P919 ML20134P929 ML20134P933
References
NUDOCS 8509090100
Download: ML20134P929 (9)

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1. o,, UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION 3 .E WASHING TON, D. C. 20555 l

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l CONffECTIrllT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET N0. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE An.endment No. 66 License No. DPR-61

1. The Nuclear Regulatory Cortnission (the Comission) has found that:

A. The application for anendment by Connecticut Yankee Atomic Power Company (the licensee) dated May 2,1983 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 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; end (11) that such activities will be conducted in compliance with the Cocinission's regulations; D.

The issuance of this amendnent 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.

8509090100 850903 PDR P ADOCK 05000213 PDR

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2. Accordinaly, the license is amended by changes to the Technical l Specifications as indicated in the attachnent to this license amen &ent and Paragraph 2.C(2) of Facility Operating License No. DPP-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendi:es A and B as revised through Amendment No. 66, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license emendment is effective as of the date of its issuance.

FORTHENUCLEARREGULATORY30FHISSION o

John \. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 3, 1985.

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ATTACHMENT T0 LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix A Technical Specification with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT II II III III

-- 3-45

-- 3-46

-- 4-33 6-22 6-22 b

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W PAGE SECTION 2.0 SAFETY LIMITS AND MAX 1 MUM SAFETY SETTINGS 2.1 Introduction 2-1 2.2 Reactor Core

• 2-1 2.3 Reactor Coolant System Pressure 2-4 2.4 Protective Instrumentation 2-5 SECTION 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Introduction 3-1 3.2 Reactor Coolant System Activity 3-2 3.3 Reacter Coolant System Operational Components 3-3 3.4 Combined Heat-up, Cooldown and Pressure Limitations 3-5 3.5 Chemical and Volume Control System 3-8 3.6 Core Cooling Systems 3-10 3.7 Minimum Water Volume and Boron Concentration in the Refueling Water Storage Tank 3-11 3.8 Turbine Cycle 3-12 3.9 Operational Safety Instrumentation and Control Systems 3-14 3.10 Control Group Insertion Limits 3-16 3.11 Containment 3-18 3.12 Station Service Power 3-21 3.13 Refueling 3-23 3.14 Primary System Leakage 3-25 3.15 Reactivity Anomalies 3-27 3,16 Isothermal Coefficient of Reactivity 3-28 3.17 Limiting Linear Heat Generation Rate 3-30 3.18 Power Distribution Monitoring and Control 3-32 3.19 Hydraulic Snubbers 3-38 3.20 Reactor Coolant System Flow, Temperature and Pressure 3-39 3.21 Safety Related Equipment Flood Protection 3-40a 3.22 Fire Protection Systems 3-41 3.23 Post Accident Instrumentation 3-45 l II Amendment No. M g ,66

w SECTION 4.0 SURVEILLANCE REQUIREMENTS ,

PAGE 4.1 Introduction 4-1 4.2 Operational Safety Items 4-2 4.3 Core Cooling Systems - Pgriodic Testing 4-3 4.4 Containment Testing 4-5 4.5 Emergency Power System Periodic Testing 4-11 4.6 Radioactive Liquid Waste Release 4-13 4.7 Radioactive Gaseous Waste Release 4-15 4.8 Auxiliary Steam Generator Feed Pump 4-17 4.9 Main Steam Isolation Valves 4-18 4.10 Inservice Inspection and Reactor Vessel Surveillance 4-19 4.11 . Deleted 4.12. High Energy Piping System Tests 4-24 4.13 Hydraulic Snubbers 4-26 4.14 Flood Protection Annunciation 4-29a 4.15 Fire Protection Systems 4-30 4.16 Post Accident Instrumentation 4-33 l SECTION 5.0 DESIGN FEATURES 5.1 Introduction 5-1 5.2 Site Description 5-1 5.3 Reactor 5.4 5-2 Containment 5-4 t

III Amendment No. 24, 27, pf, 66 l

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3.23 Post Accident Inntrum r.tetion Apolicability This specification applies to specific plant in st rument at ion required for post-accident assessments.

h Objective To ensure the instrumentation will be operable if required.

Soecification

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A. Cont ainment Mich Radiation Monitor

, c A.1 Two containment high radiation monitor channels shall be operable during modes 1, 2, 3, and 4 with:

a) The capability to measure up to 1 x 10o R/hr.

b) The alarm setpoint less than or equal 100 R/hr.

A.2 k'ith one or more channel (s) inoperable, restore the inoperable channel (s) to operable status within 7 days, or else prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 within the next 10 days outlining: the cause of the malfunction, the plans for restoring the channel to operable status, and any alternative methods for esti-mating containment dose rates during the interim.

3-45 Amendment No. 66 ,

B. Stack Wide Range Soble Gas Monitor

, B.1 One stack vide range noble gas monitor channel shall be 1

operable during modest 1, 2, 3, and 4 with:

a) The capability to measure up to 1 x 105 pC/cc of Xe-133.

b) The alarm setpoint 1,ess than or equal to the monitor reading corr'esponding to 1 pC/cc.

B.2 With less than one channel operable, return one channel to operable status within 7 days, or else prepare and i submit a Special Report to the Co==ission pursuant te l Specification 6.9.3 within the next 10 days outlining:

l the cause of the malfunction, the plans for restoring i che channel to operable status, and any alternative methods for estimating stack release rates during the interim.

Basis These specifications ensure the operability of the high range containment radiation monitors and wida range stack noble gas monitors. These monitors are required for post-accident assess-ments. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident", December 1980 and NURIG-0737,

" Clarification 'of TM1 Action Plan Requirements," November,1930.

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3-46 Amendment No. 66 I

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4.16 Post Accidsnt Instrumtntation A. Containment High Radiation Monitor A.1 Each containment high' radiation monitor channel shall be demonstrated operable by:

a) Performance of a channel check once per day, b) Performance of a channel calibration and functional test once every refueling. Calibration of the sensor with a radioactive source need only be performed for levels less than or equal to 10R/hr. Higher levels may be calibrated electronically.

B. Stack Wide Range Noble Gas Monitor B.1 The stack vide range noble gas monitor channel shall be demonstrated operable by:

a) Performance of a channel check once per day, b) Performance of a channel calibration and functional test once every 92 days.

Basis The test frequencies specified will ensure the operability of the containment and stack monitors.

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4-33 Amendment No. 66

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.3 Special reports shall be subnitted to the Regional Administrator of the Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirernents of the applicable reference specification:

a. Inservice Inspection results, Specifications (4.10) and (4.12).

b. Primary Containrent Leak Pate Results, Specification (4.4),

c. Reactor Vessel Material Surveillance Specimen Examination, Specification (4.10),

d. Steam Generator Tube Report Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

e. Post-Accident Instrumentation Operability, Specification (3.23 A and B).

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering the time interval at each power level.

b. Records and logs of prircipal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. Reports of all events which are required by regulations and Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

6-22 Amendment No. d J , 66

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