ML20100R190
| ML20100R190 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/04/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20100R192 | List: |
| References | |
| NUDOCS 9603120301 | |
| Download: ML20100R190 (8) | |
Text
.
psung
=
p
- a UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20046-0001 o%...../
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. NPF-49 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 June 29, 1995, 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.
~
9603120301 960304 PDR ADOCK 05000423 P
PDR a.
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. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendrent No. 127, 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 Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implementea within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
c.{
Phillip F. McKee, 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: March 4, 1996 0
ATTACHMENT TO LICENSE AMENDMENT NO.127 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 vertical lines indicating the areas of change.
Remove Insert 3/4 6-17 3/4 6-17 3/4 7-5 3/4 7-5 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 7-23 3/4 7-23 l
C0FTAlf9fENT SYSTEMS ELECTRIC HYDROGEN RECONBINERS LIMITING C0lWITION FOR OPERATION 3.6.4.2 Two independent Hydrogen Recombiner Systems shall be OPERABLE.
APPLICABILITY: NODES I and 2.
EllQti:
With one Hydrogen Recombiner System inoperable, restore the inoperable system to OPERABLE status within 30 days 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 />.
SURVEILLANCE REQUIRENENTS 4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE at least once each REFUELING INTERVAL by:
l a.
Deleted l
b.
Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits,
~
c.
Verifying through a visual examination that there is no evidence of
)
abnormal conditions within the recombiner enclosure (i.e.,
loose wiring or structural connections, deposits of foreign materials, etc.),
l d.
Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than 10,000 ohms, and e.
Verifying during a recombiner system functional test using containment atmospheric air at an acceptable flow rate as determined in Section 4.6.4.2.f that the gas temperature increases to greater than or equal to 1100*F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and is maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
f.
Verifying during a recombiner system functional test using containment atmospheric air that the blower would be capable of delivering at least 41.52 scfm at containment conditions of 12.47 psia and 130*F.
NILLSTONE - UNIT 3 3/4 6-17 Amendment No. J7, 77,199,127 esse
\\
PLANT SYSTEMS
.a j
SURVEILLANCE REQUIREMENTS (Continued) b.
At le'ast once per 92 days on a STAGGERED TEST BASIS by:
4 l
1)
Verifyirig that on rscirculation ficw each meter-driven pump develops a differential pressure of greater than or equal to 1460 psid when tested pursuant to Specification 4.0.5;
}
2)
Verifying that on recirculation flow the steam turbine-driven pump develops a differential pressure of greater than or equal I
to 1640 psid when the secondary steam supply pressure is i
greater than 800 psig. The provisions of Specification 4.0.4 are not applicable for entry into N00E 3.
]
c.
At least once each REFUELING INTERVAL by verifying that each auxiliary feedwater pump starts as designed automatically upon l j
j receipt of an Auxiliary Feedwater Actuation test signal.
For the steam turbine-driven auxiliary feedwater pump, the provisions of Specification 4.0.4 are not applicable for entry into N0DE 3.
l 4.7.1.2.2 An auxiliary feedwater flow path to each steam generator shall be j
demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days j
prior to entering MODE 2 by verifying flow to each steam generator.
1 1
- i l
1 i
i i
i MILLSTONE - UNIT 3 3/4 7-5 Amendment No. M. /pp.127 osee u.
, _. ~..
PLANT SYSTEMS 3/4.7.3 REACTOR PLANT C6NPONENT C0OLING WATER SYSTEM LIMITING COMITION FOR OPERATION 3.7.3 At least two independent reactor plant component cooling water safety loops shall be OPERABLE.
APPLICABILITY: NODES 1, 2, 3, and 4.
i ACTION:
With only one reactor plant component cooling water safety loop OPERABLE, re-store at least two loops 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 /> and 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 REQUIREMENTS 4.7.3 At least two reactor plant component cooling water safety loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, I
power-operated, or automatic) servicing safety-related equipment that
" is not locked, sealed, or otherwise secured in position is in its correct position; and b.
At least once each REFUELING INTERVAL by yerifying that:
l 1)
Each automatic valve actuates to its correct position on its associated Engineered Safety Feature actuation signal, and 2)
Each Component Cooling Water System pump starts automatically on an SIS test signal.
-MILLSTONE - UNIT 3 3/4 7-11 Amendment No. 127 ones
i j
. PLANT SYSTEMS i
3/4.7.4 SERVICE WATER SYSTEM i
l LIMITING C0EITION FOR OPERATION 3.7.4 At least two independent service water loops shall be OPERABLE.
APPLICABILITY: NODES 1, 2, 3, and 4.
ACTION:
Mth only one service water loop OPERABLE, restore at least two loops to DMIRABLE 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 /> and 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 REQUIRE 1ENTS 4.7.4 At least two service water loops shall be demonstrated CPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.
At least once each REFUELING INTERVAL by verifying that:
1)
Each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation signal, and 2)
Each Service Water System pump starts automatically on an SIS test signal.
MILLSTONE - UNIT 3 3/4 7-12 Amendment No.127 asse
PLANT SYSTEMS SURVEILLANCE REQUIRENENTS (Continued) 1 type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.10.f. All snubbers found i
connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.
If j
continued -operation cannot be justified, the snubber shall be
?
declared inoperable and the ACTION requirements shall be met.
l d.
Transient Event Insoection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially 4
{
damaging transients as determined from a review of operational data j
and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall j
be verified using at least one of the following:
(1) manually 1
induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its j
full range of travel.
1 e.
Functional Tests During the first refueling shutdown and at least once each REFUELING INTERVAL thereafter, a representative sample of snubbers of each j
type shall be tested using one of the following sample plans. The sample plan for each type shall be selected prior to the test period and cannot be changed during the test period.
The NRC Regional Administrator shall be notified in writing of the sample plan selected for each snubber type prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test.
For i
each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.10f., an additional 5%
of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested; or MILLSTONE - UNIT 3 3/4 7-23 Amendment M. M, #p.127 0372
-