ML20248K923
| ML20248K923 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/05/1998 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20248K925 | List: |
| References | |
| NUDOCS 9806100343 | |
| Download: ML20248K923 (7) | |
Text
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t UNITED STATES y
j NUCLEAR REGULATORY COMMISSION "s...../
t WASHINGTON, D.C. 20666 4 001
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTOt2 NUCLEAR POWER STATION. UNIT NO. 3 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 161 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
. A.
The application for amendrannt by Northeast Nuclear Energy Company, et al.
(the licensee) dated April 14,1998, as supplemented May 7,1998, and two letters dated June 4,1998, 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; l
0.
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 i
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.
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l 9806100343 990605 PDR ADOCK 05000423 p
2.
- Accordingly, the license is amended by changes to the Technical Specifications as l
indicated in tho attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 161 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in -
the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmenbi Protection Plan.
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 A
Phillip F.
cKee Deputy Director for Licensing Specie! Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
June 5, 1998 p
'N E.'4JHMENT TO LICENSE AMENDMENT NO.161 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of chanpa.
Remove Inser1 3/4 4-12 3/4 4-12 3/4 4-13 3/4 4-13 8 3/4 4-2b B 3/4 4-2b B 3/4 4-2c I
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l REACTOR' COOLANT SYSTg.
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3/4.4.4 RELIEF VALVff 1.INITING CONDIT!6N FOR OPERATION I
l 3.4.4.
Both oower-operated relief valves (PORVs) and their associated block l
valves shall be OPERABLE.
l APPLICABILITY: MODES 1, 2, and 3.
1 ACTION:
i a.
With one or both PORV(s) inoperable because of excessive seat-leakage, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) with power maintained to the block valve (s); otherwise, 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one PORV inoperable due to causes other than excessive seat leakage, within I hour either restore the PORV to OPERABLE status or close the associated blnck valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 /> and in HOT l
SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With both PORVs inoperable due to cause:, other than excessive seat leakage, within I hour either restore at least one PORV to OPERABLE status or close its associated block valve and remove power from the block valve and be in 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With one or both block valve (s) inoperable, within I hour restore the block valve (s)* to OPERABLE status, or place its associated PORV(s) control switch to "CLOSE." Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable; restore any remaining inoperable block valve to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, e.
Entry into an OPERATIONAL MODE is permitted while subject to these ACTION requirements.
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MI,L,LSTONE'- UNIT 3 3/4 4-12 Amendment No. J7, pp.161 J
RELIEF VALVES SURVEILLANCE REQUIREMENTS i
4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE by:
a.
Performance of a CHANNEL CALIBRATION at least once each REFUELING INTERVAL; and b.
Operating the velve through one complete cycle cf full travel during MODES 3 or 4 at seast once each REFUELING INTERVAL; and c.
Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV high pressurizer pressure actuation channels, but excluding valve operation, at least once each quarter; and d.
Verify the PORV high pressure automatic opening function is enabled at I
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION b.
or c. in Specification 3.4.4.
4.4.4.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by operating the valves through a complete cycle of full travel.
NILLSTONE - UNIT 3 3/4 4-13.
Amendment No. 77 J77,161 om
REACTOR C0OLANT SYSTEM BASES 3/4.4.3 PRESSURIZER (cont'd.)
The 12-hour periodic surveillance requires that during MODE 3 operatien, pressurizer level is maintained below the nominal upper limit to provide a minimum space for a steam bubble. The surveillance is performed by observing the indicated level. The 12-hour interval has been shown by operating practice to be sufficient to regularly assess level for any deviation and to ensure that a steam bubble exists in the pressurizer. Alarms are also available for early detection of abnormal level indications.
The basis for the pressurizer heater requirements is identical to MODES 1 and 2.
3/4.4.4 RELIEF VALVES The power-operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. Operat. ion of the PORVs n.inimizes the undesirable opening of the spring-loaded pressurizer Code safety valves.
Each PORV has a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable. Requiring the PORVs to be OPERABLE ensures that the capability for depressurization during safety grade cold shutdown is met.
Action statements a, b, and c distinguishes the inoperability of the power operated relief valves (PORV).
Specifically, a PORY may be designated inoperable but it may be able to automatically and manually open and close and therefo're, able to perform its function.
PORV inoperability may be due to seat leakage which does not prevent automatic or manual use and does not create the possibility for a small-break LOCA.
For these reasons, the block valve may be closed but the action requires power to be maintained to the valve. This allows quick access to the PORV for pressure control. On the other hand if a PORV is inoperable and not capable of being automatically and manually cycled, it must l
be either restored or isolated by closing the associated block valve and removing power.
Automatic operation of the PORVs is created to allow more time for operators to terminate an Inadvertent ECCS Actuation at Power. The PORVs and associated piping have been demonstrated to be qualified for water relief. Operation of the PORVs will prevent water relief from the pressurizer safety valves for which qualification for water relief has not been demonstrated.
If the PORVs are capable of automatic operation but have been declared inoperable, closure of the PORV block valve is acceptable since the Emergency Operating Procedures provide guidance to assure that the PORVs would be available to mitigate the event.
Operability and setpoint controls for the safety grade PORV opening logic are maintained in the Technical Requirements Manual.
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MILLSTONE - UNIT 3 8 3/4 4-2b Amendment No. # 7, 161
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c-l REACTOR COOLANT SYSTEN BASES RELIEF VALVES (Continued)
The prime importance for the capability to close the block valve is to isolate a stuck-open PORV. Therefore, if the block valve (s) cannot be restored to operable status within I hour, the remedial action is to place the PORV in manual control (i.e. the control switch in the "CLOSE" position) to preclude its automatic opening for an overpressure event and to avoid the potential of a stuck-open PORV at a time that the block valve is inoperable. The time allowed to restore the block valve (s) to operable status is based upon the l
remedial action time limits for incperable PORV per ACTION requirements b. and l
c.
Action statement d. does not specify closure of the block valves because such action would not likely be possible when the block valve is inoperable.
For the same reasons, reference is not made to Action statements b. and c. for the required remedial actions.
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'NILLSTONE - flNIT 3 B 3/4 4-Ec Amendment No. pp, Jpp.161 osos -
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