ML20211G679

Amend 95 to License DPR-3,modifying Tech Specs to Add Containment high-range Radiation,Pressure & Water Level Monitors & Core Exit & Reactor Vessel Head Thermocouples to Required Instrumentation List

ML20211G679
Person / Time
Site:	Yankee Rowe
Issue date:	06/05/1986
From:	Mckenna E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211G677	List: ML20211G679
References
NUDOCS 8606200073
Download: ML20211G679 (12)

Text

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/** UNITED STATES

, !'a - .JI e NUCLEAR REGULATORY COMMISSION 5 . "f # 7 E WASHINGTON, D. C. 20555 hh e

YANKEE ATOMIC ELECTRIC COMPANY DOCKET N0.50-029 -

YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-3

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

A. The applications for amendment by Yankee Atomic Electric Company

- . (the licensee) dated October 15, 1985 and October 31, 1985 comply 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:

i B606200073 060605 PDR P

ADOCK 00000029 PDR

(2) Technical Specifications The Technical Specifications contained in Appendix A as '

revised through Amendment No.95 , 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 Edcou A Ac h , %

Eileen M. McKenna, Project Manager Project Directorate #1 Division of PWR Licensing-A

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Attachment:

Changes to the Technical Specifications Date of Issuance: June 5, 1986 e

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ATTACHMENT TO LICENSE AMENDMENT N0. 95 FACILITY OPERATING LICENSE N0. DPR-3 DOCKET N0. 50-29 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 3-18 3/4 3-18

~ ' 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-23 3/4 3-23 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 6-15* 3/4 6-15*

3/4 6-16 3/4 6-16 6-22 6-22

• 0verleaf page provided to maintain document completeness. No changes contained on this page.

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TABLE 3.3-4 -

RADIATION W ITORING INSTRUMENTATION N

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% MINIMUM CHANNELS APPLICABLE ALARM MEASUREMENT INSTRUNENT OPERABLE MODES SETPOINT RANGE ACTION

1. AREA MONITORS (a) Spent Fuel Pit Area

1. Fuel Manipulator 1 (1) s 5 mR/hr or 2 x 1.0 - 50 mR/hr* 11 background, which-ever is greater (b) Containment

1. Fuel Manipulator 1 (1) s 10 mR/hr or 2 x 1.0 - 1000 mR/hr* 12 m background, which-

) ever is greater C"

2. High Range 1 1,2,3,4 s 5 R/hr 1.0 - 10 7 R/hr 15 (Also Accident -

Emergency Monitors)

2. PROCESS MONITORS (a) Containment

1. Main Coolant System 1 1,2,3,4 NA 10 - 106 cpm 13 Leakage Air Par-ticulate Monitor k (b) Radioactive Liquid R Monitors

@ 1. Steam Generator 1(2) '1, 2, 3, 4 s 80 cps or 2 x 10 - 106 ep. 14 l

$ *, Blowdown Monitors background, whichever z is greater o

• Indicated upper end of measurement range is minimum required. Actualmeasurementrankemayexceedthat stated.

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TABLE 3.3-4 (Continued) 4 TABLE NOTATION (1) When handling irradiated fuel, control rods or sources.,

(2) Per steam generator in a non-isolated loop.

> ACTION STATEMENTS ,

Aetion 11 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12. 4 Action 12 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend all operations involving CORE ALTERATIONS. l Action 13 - With the number of channels OPERABLE less than required by the

, Minimum Channels OPERABLE requirement, comply with the ACTION j requirements of Specification 3.4.5.1.

4 Action 14 - With the number of channels OPERABLE less than required by the

. . Minimum Channels OPERABLE requirement, provide an OPERABLE temporary continuous monitor within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

nocton 15 - With the number of OPERABLE Channels less than required by the j Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s),

within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and

1. either restore the inoperable Channel (s) to OPERABLE status within seven days of the event, or j 2. prepare and submit a special report to the Commission pursuant to specification 6.9.6 within fourteen days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to CPERABLE status.

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YANKEE-ROWE 3/4 3-20 Amendment No. 58, se 95 e

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TABLE 4.3-3 Eb RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS E

N A

O MODES CHANNEL IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REOUIRED

1. AREA MONITORS (a) Spent Fuel Pit Area

1. Fuel Manipulator S R M *

(b) Containment Rs 1. Fuel Manipulator

• - S R M

• y 2. High Range 3 (Also Accident Emergency Monitors S R R 1,2,3,4

2. PROCEOS MONITORS (a) Containment

1. Main Coolant System Leakage Air Particulate Monitor S R M 1, 2, 3, 4 (b) Radioactive Liquid Monitor g 1. Steam Cenerator Blowdown g Monitor S R H 1,2,3,4 5

a

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5 8 4

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• When handling irradiated fuel, control rods or sources.

.. 1 INSTRUMENTAT70N0 INCORE DETECTION SYSTEM LIMITING CONDITIONS FOR OPERUI9I 3.3.3.2, The incore detection system shall be OPERABLE with:

a. At least twelve (12) neutron detector thimbles OPERABLE. -

b. L minia.tm of two (2) OPERABLE neutron detector thimbles per core quadrant, and ,

c. Sutficient OPERABLE movable neutron detectors, drive and readoiit equipraent to map these thimbles.

APPLICABILITY: When the incore detection system is used for core power dictribution measurements.

ACTION ,,

With the incore detection systam inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILI.ANCE REQUIREMENT!: . n 4.3.3.2 The incoro neutron tectors at all be demonstrated OPERABLE by normalizing each detector--cutput to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use for core power distribution measurements.

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f YANKEE-ROWE 3/4 3-23 Amendment No. . J (, /I. / f 95 r!

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TABLE 3.3-7 Accident Monitorint Instrumentation Total No. Minimum Channels Instrument Of Channels Operable

1. Pressurizer Water Level 2 1

2. Auxiliary Feedwater Flow Rate 4 3 e

3. Main Coolant System Subcooling 1 1 Margin Monitor

4. PORY Position Indicator (Acoustic 1 1 Accelerometer)

5. PORY Position Indicator (Temperature 1 0 Indication, RTD)

6. PORV Block Valve Position Indicator 1 1

7. Safety Valve Position Indicator 1 1 (Acoustic Accelerometer)

8. Safety Valve Position Indicator 1 0 (Temperature Indication, RTD)

9. Containment Water Level 2 1 (Wide-Range)

10. In Core Thermocouple Channels 8 1 in each (Core Exit Thermocouples) of 3 Core Quadrants

11. Containment Pressure (Wide-Range) 2 1

12. Reactor Vessel Head Thermocouples 2 1 t

YANKEE-ROWE 3/4 3-30 AmendmentNo./ 95

TABLE 4.3-5 Accident Monitorinz Instrumentation Surveillance Reauirements Channel

• Channel Instrument Check Calibration

1. Pressurizer Water Level M R

2. Auxiliary Feedwater Flow Rate M R

3. Main Coolant System Subcooling M R '

Margin Monitor

4. PORV Position Indicator (Acoustic M R Accelerometer)

5. PORV Position Indicator (Temperature M R Indication, RTD)

6. PORY Block Valve Position Indicator M R

_ , 7. Safety Valve Position Indicator M R (Acoustic Accelerometer)

8. Safety Valve Position Indicator M R (Temperature Indication, RTD)

9. Containment Water Level M R (Wide-Range)

10. In Core Thermocouple Channels M R (Core Exit Thermocouples)

11. Containment Pressure (Wide-Range) M R

12. Reactor Vessel Head Thermocouples M R YANKEE-ROWE 3/4 3-31 Amendment No. pd' 95

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TABLE 3.6-1 (Continued)

TABLE NOTATION 1

(1) T.S. 4.6.1.1.a.1 not applicable while in Modes 1 or 2, due to ALARA considerations. ~

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(2) Valves may be open under administrative control while in Mode'4.

(3) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for containment air charge.

(4) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for neutron shield tank leakage test.

(5) Normally open and closed by administrative controls.

(6) CA-V-755 may be unlocked when personnel are in the vapor Container.

Valvt may be open while in Modes 1, 2, 3, or 4 for depressurization of the V.C. personnel hatch during containment access or for testing.

(7) CH-MOV-522 may be energized under administrative control.

(8) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for surveillance testing.

(9) T.S. 4.6.1.1.a.1 not applicable while in Modes 1, 2, 3, 4, due to ALARA C' considerations.

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(10) Containment sample valves (VD-V-1107 and VD-V-1108) and their test taps (VD-V-902 and VD-V-909) may be opened under administrative control in order to sample containment air.

(11) The ACTION statements of T.S. 3.6.2 and 3.0.3 do not apply.

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(12) Secondary isolation valves may be open under administrative controls.

3/4 6-15 Amendment No.86 YANKEE-RDWE

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COhTAINNENT SYSTEMS 3/4.6.3 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS l LIMI_ TING CONDITION FOR OPERATION 3.6.3.1 Two independent containment hydrogen monitors shall be OPERABLE.

APPLICABILITY: MODES 1 and 2 i ACTION:

a. With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. With both hydrogen monitors inoperable, restore at least one monitor to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.6.3.1 Each hydrogen monitor shall be demonstrated OPERABLE by the peciurtr.ance of the following:

a. At least once per 31 days by performance of a FUNCTIONAL TEST on each monitor by admitting a sample gas and verifying upscale indicator

vement. Also, verify High Hydrogen alarm function on the Comsip monitor,

b. At least once per (S. days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing a percentage of hydrogen, balance nitrogen that are appropriate for the analyzer being calibrated.

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, l YANKEE-ROWE 3/4 6-16 Amendment No. 95 i

ADMINISTRATIVE CONTROLS ,

The Radioactive Effluent Release Reports shall include any changes made j during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFF-SITE DOSE CALCULATION MANUAL (0DCM), as well as a listing of new  !

locations for dose calculations and/or environmental monitoring  !

identified by the land use census pursuant to Specification 3.12.2. l l

6.9.6 Special reports shall be submitted to the Director of the Office of l j Inspection and Enforcement Regional Office within the time period specified [

for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:  !

a. (Deleted). i i

b. ECCS Actuation, Specifications 3.4.2 and 3.5.3.

Inoperable Meteorological Monitoring Instrumentation, c.

Specification 3.3.3.3. .

. . d. Sealed Source leakage in excess of limits, Specification 3.7.6.

e. Fire Detection Instrumentation, Specification 3.3.3.4.

f. Fire Suppression Systems Specifications 3.7.10.1, 3.7.10.2, 3.7.10.3, 3.7.10.5 and 3.7.10.6. ,

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g. Liquid Effluents, Specifications 3.11.1.2 and 3.11.1.3.

h. Gaseous Effluents. Specifications 3.11.2.2, 3.11.2.3 and 3.11.2.4. f I

1. Total Dose, Specification 3.11.4.

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j. Radiological Environmental Monitoring, Specification 3.12.1.  ;

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k. Radiation Monitoring, Specification 3.3.3.1.

6.10 RECORD RETENTION ,

6.10.1 The following records shall be retained for at least five years: j

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

b. Records and logs of principal maintenance activities, inspection  !

repair and replacement of principal items of equipment related to nuclear safety.

c. ALL REPORTABLE OCCURRENCE reports submitted to the COMMISSION.

d. Records of surveillance activities, inepections and calkbrations required by these Technical Specifications. .

YANKEE-ROWE 6-22 Amendment No. 6[, p6', g 95 i i

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