ML20198P938
| ML20198P938 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (NPF-49-A-155) |
| Issue date: | 12/24/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198P942 | List: |
| References | |
| NUDOCS 9801220297 | |
| Download: ML20198P938 (9) | |
Text
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t UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. *am aaa1
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~ NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 155 License No. NPF-49 P
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 October 15, 1997, 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.
9901220297 971224 l
PDR ADOCK 05000423 P
.. 2.
Accordingly, the license is amendad by changes to the Technical Specifications as indicated in the attachmant to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read " follows:
(2)
Technical.Soecifications The Technical Specifications contained in Appendix A, as revised.
through Amendment No.155, and the Environmental Protection Plan contained in Appendix 0, 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 Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, s.o be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 24, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. - 155 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications, with theattachedpages. The revised pages are identified by amendment nimber and contain vertica lines indicating the areas of change.
Remove Insert 3/4 1-15 3/4 1-15 3/4 1-16 3/4 1-16 3/4 5-5 3/4 5-5 3/4 5-6 3/4 5-6 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13
REACTIVITY CONTROL SYSTEMS CHARtlNR PUMP - SillTD0ldN LIMITING CONDITION FOR OPERATION.
3.1.2.3 One charging pump in the boron injection flow path required by
-Si>ecification 3.1.2.1 shall be OPERABLE and capable of >eing powered from an OPERABLE emergency power source.
APPLICABILITY: MODES 5 and 6.
Ell 3:
With no charging pump OPERABLE or capable of being powered from an OPERABLE emergency power source, surpend All operations involving CORE ALTERATIONS or.
Positive reactivity changes.
SURVEILLANCE REQUIRENENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying that its developed head at the test flow point is greater than or I equal to the required developed head when tested pursuant to Specification l
4.0.5.
4.1.2.3.2 All charging pumps, excluding the above required OPERABLE pump, shall be demonstrated inoperable at least once per 31-days, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position.
t NILL 5 TONE - UNIT 3 3/41-15 Amer.dment No. pp. $P. 155 0567
REACTIVITY CONTROL SYSTEMS CHARD!NB PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two* charging pumps shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACllati:
With only one charging pum) OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least the limit as shown in Figure 3.1-4 at 200*F within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />si restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDDWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS l
4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying that each pump's developed head at the test flow point is greater i
than or equal to the required developed head when tested pursuant to i
Specification 4.0.5.
i 4.1.2.4.2 All charging pumps, except the above allowed OPERABLE pump, shall be demonstrated inoperable at least once per 31 days whenever the l
temperature of one or more of the Reactor Coolant System (RCS) cold legs is less than or equal to 350*F by verifying that the motor circuit breakers are secured in the open position.
l l
l l
i i
- A maximum of one centrifugal charging pump shall be OPERABLC whenever the-temperature of one or more of the RCS cold legs is less than or equal to 1
350*F.
j i
1 MILLSTONE - UNIT 3 3/4 1-16 Amendment No. 77 155 -
i 0557 S
- 4-EMERRENCY CORE C0OLING SYSTEMS
)
SURVEILLANCE REQUIREMENTS (Continued) 2)
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion, At least once each REFUELING INTERVAL by:
- e. -
1)
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection actuation test signal, and 2)
Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
a)
Centrifugal charging pump, b)
Safety Injection pump, and 4
c)
RHR pump.
3)
Verifying that the pa 4bal Heat Removal pumps stop automatically upon rec /
7,* a Low-Low RWST Level test signal.
f.
By verifying that each of the following pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5:
1)
Centrifugal charging pump 2)
Safety Injection pump 3)
RHR pump 4)
Containment recirculation pump g.
By verifying the correct position of each electrical and mechanical position stop for the following ECCS throttle valves /or 1)
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation ur maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)
At least once each REFUELING INTERVAL.
ECCS Throttle Valves Valve Newber Valve Number
-3SIH*V6 3SIH*V25 3 Sill *V7 35!H*V27 Mgl5 TONE-UNIT 3 3/45-5 Amendment No. 77, 115, 155
i EMERGENCY CORE COOLING SYSTEMS SURVEILLANCEREQUIREMENTS(Continued)
ECCS Throttle Valves Valve Nnaher Valve Number 351H*V8 3SIH*V107 351H*Vg 3SlH*V108 3511t*V21 351H*V109 3SIH*V23 351H* Vill h.
By performing a flow balance test following completion of modifications to the ECCS-subsystems that alter the subsystem flow characteristics and verifying that:
1)
For centrifugal charging pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 310.5 gpm, l and b)
The total pump flow rate is less than or equal to 560 gpm.
2)
For Safety Injection pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 423.4 gpm, l and b)
The total pump flow rate is less than or equal to 675 gpm.
3)
For RHR pump lires, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3976 gpm.
Ngl 5 TONE-UNIT 3 3/4 5-6 Amendment No. JP, ygg, 155
~
CONTAINMENT SYSTEMS 3/4.5.2 - DEPREssuR12 VION AND COOLING SYSTEMS CONTAINMDff OUENCH SPRAY SYSTEN -
LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Quench Spray subsystems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
El1Qti:
With one Containment Quench 5) ray subsystem inoperable, restore the inoperable system to OPERABLE status wit 11n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 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 COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
EURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Quench Spray subsystem shall be demonstrated OPERABLE:
a.
At least once per 31 days:
1)
Verifying that each valve path (manual, power
- operated, or automatic) in the flow is not
- locked, sealed, or otherwise secured in position, is in its correct position; and 2)
Verifying the temperature of the borated water in the refueling water storage tank is between 40'F and 50*F.
b.
By verifying that each pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5; At le'ast once each REFUELING INTERVAL, by:
c.
1)
Verifying that each automatic valve in the flow path actuates to its correct position on a CDA test signal, and 2)
Verifying that each spray pump starts automatically on a CDA test signal.
d.
At least once per 10 years by performing an air or smoke flow te-st through each spray header and verifying each spray nozzle is unobstructed.
NJLSTONE-UNIT 3 3/4 6-12 Amendment No. p. _ pp, Jpp, Jgg, 155
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$0NTAINNENT SYSTEMS RECIRCULATION SPRAY SYSTEN LINITING CONDITION FOR OPERATION 3.6.2.2 Two independent Pecirculation Spray Systems shall
- .,e OPERABLE.
APPLICABILITY: MODES I, 2, 3, and 4.
ACTION:
With one Recirculation Spray System inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 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 />; restore the inoperable Recirculation Spray System 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 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIRLNENTS 4.6.2.2 Each Recirculation Spray System shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) 1.. the flow path is not locked, sealed, or otherwise secured in position, is in its correct position; b.
By verifying that each pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5; c.
At least once each REFUELING INTERVAL by verifying that on a CDA test signal, each recirculation spray pump starts automatically after a 660 120 second delay; d.
At least cace each REFUELING INTERVAL, by verifying that each automatic valve in the flow path actuates to its correct position on a CDA test signal; and e.
At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
l l
M!gl5 TONE-UNIT 3 3/46-13 Amendment No. pp, Jpp, Jgg,155
..