ML20116K734
| ML20116K734 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/13/1996 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20116K735 | List: |
| References | |
| NUDOCS 9608150203 | |
| Download: ML20116K734 (6) | |
Text
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4 onucog y-1 UNITED STATES g
g NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20665 4001
'49.....,o NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NVCLEAR POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated July 3, 1996, complies 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.
9608150203 960813 PDR ADOCK 05000336 P
- 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-65 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 201, 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 issuance, to be implemented within 30 days of issuance.
FOR THE N CLEAR REGULATORY COMMISSION Phillip F Kee, Director Northeast Utilities Project Directorate Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 13, 1996
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ATTACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages..The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 9-1 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-la
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9 /4. s RErurLING OPERATIDME 3/4.9.1 BORON c0NCENTRATfDNS LIMITING CONDITION FOR OPERATION l
3.9.1 with the reactor vessel head unbolted or removed, the boron concentration of the Reactor Coolant System and the refueling canal shall be maintained sufficient to ensure that the more restrictive of following reactivity conditions is met:
a.
Either a K,, of 0.95 or less, or b.
A boron concentration of greater than or equal to 1720 ppm.
APPLfcABILTTY:
MODE 6*.
AEII2H:
With the requirements of the above specification not satisfied, within 15 minutes suspend all operations involving CORE ALTERATIONS or positive 1
reactivity changes and initiate and continue boration at greater than or aqual to 40 rpm of boric acid solution at or greater than the required refueling water storage tank concentration (ppm) until F, is reduced to less than or equal to 0.95 or the boren concentration is r,estored to greater than or equal to 1720 ppm, whichever is the more restrictive.
The provisions of Specification 3.0.3 are not applicable.
SURVEZLLANCE REQUIREMENTS 4.9.1.1 The more restIictive of the above two reactivity conditions shall be determined prior to:
Removing or unbolting the reactor vessel head, and a.
b.
Withdrawal of any full length CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.
4.9.2.2 The boron concentration of the reactor coolant system ** and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4.9.2.3 The boron concentration in the cold leg side of the steam generators shall be determined to be greater than or equal to 1300 ppm prior to entering MODE 6.
'The reactor shall be maintained in MODE 6 whenever the reactor vessel head is unbolted or removed and fuel is in the reactor vessel.
- For the Cycle 13 mid cycle core offload activities, it is acceptable for the boron concentration of the water volumes in the steam generators and connecting piping to be as low as 1300 ppm.
gLLSTONE-UNIT 2 3/4 9-1 Amendment No. 201 1
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION l
The limitations on reactivity conditions during REFUELING ensure that:
- 1) the reactor will remain subcritical during CORE ALTERATIONS, and
- 2) sufficient boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
For the Cycle 13 mid-cycle core offload activities, the baron concentration of the water volumes in the steam generators and connecting piping may be as low as 1300 ppm.
During REFUELING and/or CORE ALTERATIONS, the water volumes in the steam generators and connecting piping are stagnant and do not readily mix with the water in the reactor vessel. The water volumes in the pressurizer and connecting piping, shutdown cooling system (including reactor vessel and connecting piping), and refueling pool shall be maintained greater than 1950
^
ppm.
A boron dilution analysis has been performed which accounts for dilution of the shutdown cooling system with the water volumes from the steam generators and connecting piping. This analysis demonstrates that, in the unlikely event in which all of the water in the steam generators and connecting piping mixes with the water in the shutdown cooling system, the resulting shutdown cooling system boron concentration will remain greater than the required refueling boron concentration.
The surveillance requirement to verify that the boron concentration in the steam generators is greater than 1300 ppm prior to entering MODE 6 is consistent with the assumptions of the boron dilution calculation. The sample points are only located on the cold leg side of the steam generators. These sample points are representative of the water volumes in the steam generators (both hot and celd legs) and their connectirq piping, based on the fact that uniform mixing of these water volumes at a boron concentration of approximately 1320 ppm had occurred prior to shutting off the reactor coolant pumps.
In March 1996, the reactor coolant system was drained al.d subsequently refilled with water having a boron concentration greater than or equal to 1320 ppm. The boron concentration of the water in the steam generators and connecting piping is greater than 1300 ppm.
3/4.9.2 INSTRUMENTATION The OPERABIL1TY of the source range neutron flux monitors ensures that redundant monitort :9 capability is available to detect changes in the reactiv-ity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated fuel ensures that sufficient time has elapsed to allow the radioac-tive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the accident analyses.
{IgLSTONE-UNIT 2 B 3/4 9-1 Amendment No. 77. J M. # 7, 201
BASES (continued) l The requirement that the spent fuel pool bulk temperature be maintained 4
below 140*F ensures that high water temperature will not degrade resin in the spent fuel pool domineralizers and that the temperature and humidity above the 4
pool are compatible with personnel comfort and safety requirements. Addition-ally, the requirement ensures that the desi cooling system, liner / building structures, gn temperature of the fuel pool and racks are not exceeded.
The requirement for the reactor to remain in MODE 5 or 6 until the most recent 1/3 core offload has decayed 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> ensures that alternate cooling is available during this time to cool the spent fuel pool should a failure occur in the spent fuel pool cooling system. The shutdown cooling (SDC) system is a high ca)acity system; that is, one train is sufficient to cool both the core and tle s)ent fuel pool should a failure occur in the spent fuel pool cooling system wit 11n 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> from reactor shutdown.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure l
restrictions are sufficient to restrict radioactive material release from a fuel element ru)ture based upon the lack of containment pressurization poten-tial while in tie REFUELING MODE.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel. can be promptly informed of significant changes in the facility status or core reactivity condition during fuel or CEA movement within the reactor pressure vessel.
i gIgLSTONE-UNIT 2 B 3/4 9-la Amendment No. 77, JJJ, JJ7, 201