ML20083P575
| ML20083P575 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/18/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083P580 | List: |
| References | |
| NUDOCS 9505240281 | |
| Download: ML20083P575 (6) | |
Text
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4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-4001 os.,...../
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.189 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 21, 1995, 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; 1
B.
The facility will operate in conformity with the application, the 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 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 Comission's regulations and all applicable requirements have been satisfied.
9505240281 950510 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.189, 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 NUCLEAR REGULATORY COMMISSION h
~
Phillip P'. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
May 18, 1995
i ATTACHMENT TO LICENSE AMENDMENT NO. 189 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 1-13 3/4 1-13 B 3/4 1-3 8 3/4 1-3 B 3/4 1-3a B 3/4 1-3a l
1 REACTIVITY CONTROL SYSTEMS CHARGING PUMP 3_.. OPERATING LIMITING COMITION FOR OPERATION 3.1.2.4 At least two** charging pumps shall be OPERABLE.
. APPLICABILITY: MODES 1, 2, 3 and 4*.
l ACTION:
With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; restore at least two charging pum)s to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN wit 11n the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.4.1 Two charging pumps shall be demonstrated OPERABLE at least once per 31 days on a STAGGERED TEST BASIS by:
a.
Starting (unless already operating) each pump from the control room, and b.
Verifying that each pump operates for at least 15 minutes.
4.1.2.4.2 One charging pump shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is
< 300*f by verifying that the motor circuit breaker is in the open position.
i i
- The provisions of Specification 3.0.4 and 4.0.4 are not applicable for entry into MODE 4 for the charging pump that is inoperable pursuant to Specification 3.1.2.3 provided the charging pump is restored to OPERABLE status within at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to entering MODE 3, whichever comes first.
1 MILLSTONE - UNIT 2 3/4 1-13 Amendment No. Jp), 189 0191
.J
i BASES 3/4.1.2 BORATION SYSTEMS (Continued)
The analysis to determine the boration requirements assumed that the Reactor Coolant System is borated concurrently with cooldown.
In the limiting situation when letdown is not available, the cooldown is assumed to be initiated within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> and cooldown to 220'F, is completed in the next 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
With the RCS temperature below 200'F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The boron capability required below 200*F is based upon providing a SHUTDOWN MARGIN within the limit specified in the CORE OPERATING LIMITS REPORT at 140*F after xenon decay.
This condition requires either 3750 gallons of 2.5% boric acid solution from the boric acid tanks or 57,300 gallons of 1720 ppm borated water from the refueling water storage tank.
The maximum boron concentration requirement (3.5%) and the minimum temperature requirement (55'F) for the Boric Acid Storage Tank ensures that boron does not precipitate in the Boric Acid System.
The daily surveillance requirement provides sufficient assurance that the temperature of the tank will be maintained higher than 55'F at all times.
A minimum boron concentration of 1720 ppm is required in the RWST at all times in order to satisfy safety analysis assumptions for boron dilution iricidents and other transients using the RWST as a borated water source as well as the analysis assumption to determine the boration requirement to ensure adequate shutdown margin.
A maximum of two charging pumps OPERABLE, when RCS temperature is less than 300*F, ensures that the maximum inadvertent dilution flow rate as assumed in the boron dilution analysis is 88 gallons per minute.
The requirements for maximum pumping capability to reduce shutdown risk and low temperature overpressure protection are met by balancing the number of OPERABLE pumps with PORVs and RCS vents. An LTOP accident scenario assumes all 0PERABLE pumps start, one relief path fails, and RCS pressure then must remain less than the 10CFR50, Appendix G limits.
For shutdown risk reduction, it is desirable to have the maximum pump capacity and maintain the RCS full (not vented).
The scenarios considered by these technical specifications are as follows:
(1) A pumping capability of I charging and 1 HPSI pump with relief from 2 PORVs (to account for single failure); (2) pumping capacity of 2 charging l pumps and 1 HPSI pump or 2 charging pumps and 2 HPSI pumps with relief from an RCS passive vent of greater than or equal to 2.8 square inches. To further reduce shutdown risk by maximizing pumping capacity, a HPSI pump may be made inoperable but available at short notice by shutting its discharge valve with the key lock on the control panel.
MILLSTONE - UNIT 2 8 3/4 1-3 Amendment No. 75, pJ, 72, JJp, om 15,119,199,199, 189
BASES 3/4.1.2 B0 RATION SYSTEMS (Continued)
The provision in Specification 3.1.2.4 that Specifications 3.0.4 and 4.C.4 are not applicable for entry into MODE 4 is provided to allow for closing the motor circuit breaker and subsequent testing of the inoperable charging pump.
Specification 3.1.2.3, which is applicable to MODES 5 and 6, requires that one charging pump be OPERABLE.
Specification 3.1.2.4 requires that at least two charging pumps be OPERABLE in MODES 1, 2, 3, and 4.
The exception from Specification 3.0,4 and 4.0.4 will allow Hillstone Unit No. 2 to enter into MODE 4 and test the inoperable charging pump and declare it OPERABLE.
3/4.1.3 MOVEABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.
The ACTION statements applicable to an immovable or untrippable CEA and to a large misalignment (2 20 steps) of two or more CEAs, require a prompt shutdown of the reactor since either MILLSTONE - UNIT 2 B 3/4 1-3a Amendment No. pJ, JJp, Jpp,189 0192
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