ML20082B699
| ML20082B699 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-65-A-186) |
| Issue date: | 03/27/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082B701 | List: |
| References | |
| NUDOCS 9504050276 | |
| Download: ML20082B699 (7) | |
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UNITED STATES y
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,j NUCLEAR REGULATORY COMMlbSION WASHINGTON, D.C. 2065H001
'+9.....,d NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 186 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated April 22, 1994,-
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 i
provisions of the Act, and the rules and regulations of the Comission; 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 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 l
E.
The issuance of this Omendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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9504050276 950327 PDR ADOCK 05000336 P
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_ Accordingl. the license is amended by changes to the Technical 3
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.186, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMISSION Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
March 27, 1995 L
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i ATTACHMENT TO LICENSE AMENDMENT N0.186 l
FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical 1,ines indicating the areas of change.
j Remove Insert i
j 3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 3/4 3-54 3/4 3-54 3/4 3-55 2/4 3-55 i
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TABLE 3.3-12 RADI0 ACTIVE LIOUID EFFLUENT MON'ITORING INSTRUMENTATION ALARM MININUM i SETPOINT INSTRUMENT DfER88LE RE0UIRED APPLICABILITY ETEN l.
Gross Radioactivity Monitors Providing l
Automatic Termination of Release
- a. Clean Liquid Radwaste Effluent Line 1
Yes 1
- b. Aerated Liquid Radwaste Effluent Line 1
Yes 1
c.
Steam Generator Blowdown Monitor 1
Yes 2
- d. Condensate Polishing Facility Waste
.Neut Sump 1
Yes 1
2.
Gross Radioactivity Monitors Not Providing Automatic Termination of Release a.
Reactor Building Closed Cooling Water Monitor #
1 Yes 3
3.
Flow Rate Measurements
- a. Clean Liquid Radwaste Effluent Line 1
No 4
- b. Aerated Liquid Radwaste Effluent Line 1
No 4
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- c. Condensate Polishing Facility Waste Neut Sump Discharge Line 1
No 4
- d. Dilution Water Flow No
- e. Steam Generator Blowdown Line No m
MILLSTONE - UNIT 2 3/4 3-51 Amendment No. Jpp,186 8071
TABLE 3.3-12 (Continued)
RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION Table Notes At all times - which means that channels shall be OPERA 8tE and in service on a continuous, uninterrupted basis, except that outages are permitted, for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, for the purpose of maintenance and perfomance of required tests, checks, calibrations, or sampling.
9eleted.
Modes 1-5 and Mode 6 when pathway is being used except that outages are pensitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the purpose of maintenance and performance of required tests, checks, calibrations, or sampling.
Since the only source of service water contamination is the reactor building closed cooling water, monitoring of the closed cooling water and conservative leakage assumptions will provide adequate control of service water effluents.
The dilution water is detemined by the use of condenser cooling water and service water pump status. Only those pumps actually discharging to the quarry at the time of release are included.
Pump status is only reviewed for purposes of determining flows.
fif Detemined by the use of valve curves and/or make up flow rates for the purpose of determining flows only.
MA Not applicable.
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p MILLSTONE - UNIT 2 3/4 3-52 Amendment No. J M, J 5.186 9971 i
(.-. - - - - - -
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TABLE 4.3-12 j
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION-SURVEILLANCE REQUIREMENTS i
CHANNEL i
CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK QEE CALIBRATION TEST l
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GROSS RADI0 ACTIVITY MONITORS i
PROVIDING ALARM AUTOMATIC TERMINATION 0F RELEASE 1.'
- a. Clean Liquid Radwasta j
Effluent Line D*
P R(1)
Q(2) i
- b. Aerated Liquid Radwaste j
Effluent Line D*
P R(1)
Q(2) 1 i
- c. Steam Generator Blowdown i
Monitor D*
M R(1)
Q(2) i I
- d. Deleted
- e. Condensate Polishing Facility -
Waste Neut Sump D*
P R(1)
Q(2) 4 l
'2.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT T
PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Reactor Building Closed
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Cooling Water D*
M R(1)
Q(2)
)
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- 3. FLOW RATE NEASUREMENT DEVICIS 4
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- a. Clean Liquid Radwaste Line D*
NA R
Q J
- b. /n ated Liquid Radwaste Line D*
NA R
Q
- c. Condensate Polishing Facility -
Waste Neut Sump Line D*
NA R
Q l
- d. Dilution Water Flow D(4)
NA NA NA
- e. Steam Generator Blowdown j
Line D(4)
NA NA NA i
MILLSTONE - UNIT 2 3/43-54 Amendment No. Jpp.186 0072 1
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TABLE 4.3-12 j
(Continued)
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TABLE NOTATIONS i
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- During releases via this pathway and when the monitor is r' quired j
OPERA 8LE per Table 3.3-12. The CHANNEL CHECK should be done wna the j
discharge is in progress.
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- Not Applicable.
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'(1) - Calibration shall include the use of a known radioactive - liquid or solid source which is traceable to an N85 source.
I (2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control roon j
alarm annunciation occurs if any of the following exist:
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- a. Instrument indicates measured levels above the alars/ trip j
setpoint.
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- b. Instrument indicates a downscale or circuit failure.
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- Automatic isolation of the discharge stream shall also be demonstrated for this case for each monitor except the reactor
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building closed cooling water monitor.
j (3) - Deleted.
l (4)
Pump or valve status, as apropriate, shall be checked daily for the j
purposes of determining flow rates.
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i MILLSTONE - UNIT 2 3/4 3-55 Amendment No. JM,186 0072 1
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