ML20217Q614
| ML20217Q614 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/27/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217Q618 | List: |
| References | |
| NUDOCS 9709030271 | |
| Download: ML20217Q614 (6) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _
a a'ovy p-
- t UNITED STATES NUCLEAR REGULATORY COMMISSION o
- t, WASHINGTON, D.C. souHoot
- ...+
NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY IllE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 tilLLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FAClll1Y OPERATING LICENSE Amendment No. 207 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Com)any, et al. (the licensee) dated November 20, 1995, complies wit 1 the standards and requirements of the Atomic Enerfv Act of 1954, as amended (the Act), and the Commission's rules ini 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)d without endangering the health that the activities authorized by this amendment can be conducte 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 a;nlicable 4
j requirements have been satisfied.
- ?rMBau?d8Bjj;t6 P
2-Accordingly ical Specifications as indicated-in the attachment to thisFacility Ope 2.
to the Techn license amendment, and paragraph 2.C.
No. DPR-65 is hereby amended to read a(2)follows:of Facility Operating License s
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 207, are hereby incorporated in the license. The licenses shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance to be implemented within 60 days of its issuance.
FOR TH NVCLEAR REGULATORY COMMISSION f
Phillip F. McKee Deputy Director-for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1997 i
ATTACHMENT TO LICENSE AMENDMfNT NO. 207 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Aspendix A, Technical Specifications, and the Operating License with the attac1ed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
EtBQXA Insert 3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 3/4 3-53 3/4 3-53
TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRWOTATION
.=
EF ALARM C
MININUM i SETPOINT y
INSTRUMrNT OPERABLE REQUIRED APPLICABILITY ACTION m
1.
Gross Radioactivity Monitors Providing e
g Automatic Termination of Release
[
a.
Clean Liquid Radwaste Effluent Line 1
Yes 1
- b. Aerated Liquid Radwaste Effluent Line 1
Yes I
- c. Steam Generator Blowdown Monitor I
Yes 2
l
- d. Condensate Polishing Facility Waste Neut Sump 1
Yes I
2.
-Gross Radioactivity Monitors Not Providing Automatic Termination of Release a.
Reactor Building Closed Cooling Water Monitorf 1
Yes 3
3.
Flow Rate Measurements
- a. Clean Liquid Radwaste Effluent Lina 1
No 4
X
- b. Aerated Liquid Radwaste Effluent Line I
No 4
55 c.
Condensate Polishing Facility Waste Neut Sump Discharge Line 1
No 4
z?
- d. Dilution Water Flow ff No NA wE e.
Steam Generator Blowdown Line fif No M4 4?
8
~
I
TABLE 3.3-12 (Continued)
E RADI0 ACTIVE LIOUID EFFLUDIT IUlITORING IftSTIMEITATIGI k
Table flotes At all times - which means that channels shall be OPUtABLE and in service on a continuous, uninterrupted basis, except that estages 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 performance of required tests, checks, calibrations, or sampling.
c.
Deleted.
hours for the purpose of maintenance and performance of required tests, checks, calibrations, l Modes 1-6 when pathway is being used except that estages are permitted for a maximum of 12 or sampling.
Modes 1-4, 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 performance of required tests, checks, calibrations, or sampling.
-t*
Since the only source of service water contamination is the reactor building closed cooling Y
water, monitoring of the closed cooling water and conservativc leakage assumptions will g
provide adequate control of service water effluents.
The dilution water is determined 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.
Determined by the use of valve curves and/or make up flow rates for the purpose of 1
5 determining flows only.
A l
NA flot applicable.
x*
%?
M
?
4?
8
~
m_
TABLE 3.3 12 (Continued)
ACTION STATEMENTS ACTION 1: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that best efforts are made to repair the 1
instrument and that prior to initiating a release 1.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1: and 2.
The original release rate calculations and discharge valving are independently verified by a second individual.
ACTION 2: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either:
1.
Suspend all effluent releases via this pathway, or 2.
Make best efforts to repair the instrument and obtain grab samples and analyze for gross radioactivity (b a lower limit of detection of at least 3 x 10, eta or gamma) at pC1/ml;
- a. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is > 0.01 pCi/gm DOSE EQUIVALENT l-131.
- b. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is s 0.01 pCi/gm DOSE EQUIVALENT l-131.
ACTION 3: With the number of channels OPERABLE less than required by the Minimuia Channels OPERABLE recuirement, effluent releases via this Pathway may continue providec that best efforts are made to repab the instrument ani that once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples of the service water effluent are collected and analyzed for gross radio-activity #Ci/ml.(beta or gamma) at a lower limit of detection of at least 3 x 10 ACTION 4: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE recuirement, effluent releases via this pathway may continue providec that best efforts are made to re) air the instrument and that the flow rate is estimated once per 41ours during actual releases. Pump performance curves may be used to estimate flow.
MILLSTONE - UNIT 2 3/43-53 Amendment No. Jpf, 207 0129
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