ML20246F375
| ML20246F375 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/02/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246F373 | List: |
| References | |
| NUDOCS 8905120215 | |
| Download: ML20246F375 (8) | |
Text
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UMITED STATES 5
i NUCLEAR REGULATORY COMM'SSION 3 v
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WASHINGT ON, D. C. 20555 NORTHEAST NUCLEAR EFERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
31 License No. DPP-21 1.
The Nucir.or Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Compary (thelicensee),datedJanuary 24, 1989, complies with the standards and requirements of the Atorde Energy Act of 1954, as emended (the Act}, and the Comission's rules and regulations set forth in 10 CFR Chapter I; E:. -
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 reascnable assurance (i) that the activities authorized by this amendment can be conducted without ercangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulatiers; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in eccorcerce with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8905120215 890502 ADOCK0500g5 DR
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' j 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
I and paragraph 2.C.(2) of Facility Operating License No. DPR-21 is hereby amended to read as follows:
j (2) Technical Specifications-The Technical Specifications contained in Appendix A, as revised through Amendrrr,t fio. 31, are hereby incorporated in the license.
i The licensee c'1all 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 oh 7. Stolz, Directo Pr ect Directorate vision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 2, 1989
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ATTACHMENT TO LICENSE AMENDMENT NO. 31 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert I
3/4 5-1 3/4 5-1 3/4 5-3 3/4 5-3 3/4 5-8 3/4 5-8 3/4 5-9 3/4 5-9 3/4 7 3/4 7-12
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'!"TT!Ne rnN?! TION FOR OPERATION 2.5 CORE AND CONTAINMENT COOLING SYSTEMS Arnlicabilitv:
- Applies to the operational status of the emergency cooling subsystems.
Obiective:
To assure adequate cooling capability for heat removal in the event of a loss of coolant accident or isolation from the normal reactor heat sink.
Specification:
A.
Core Sprav and LPCI Subsystems 1.
Except as specified in 3. 5. A. 2, 3.5.F.6, and 3.5.F.7, both core l
. spray subsystems shall be operable whenever irradiated fuel is-in the reactor vessel.
2.
From and after the date that one of the core spray subsystems is made or found to be inoperable for any reason, reactor operation is permissible only during the. succeeding fifteen days unless ~ such subsystem is sooner made operable, provided that during such fifteen days all active components of the other core spray subsystem and the LpCI subsystem and both emergency-power sources required for operation of such components, if no external source of power were available, shall be operable.
3.
Except as specified in 3.5.A.4; 3.5.B.3' 4, 5; 3.5.F.6; and 3.5.F.7, l
the LPCI' subsystem shall be operable whenever irradiated fuel is in -
the reactor vessel.
4.
From and after the date that one of the LPCI pumps is made or found to be inoperable, for any reason, reactor operation is permissible only during the succeeding 30 days unless such pump is sooner made operable, provided that during such thirty days the remaining active components of the LPCI and containment cooling subsystem and all active components of both core spray subsystems and both emergency power sources required for operation of such components, if - no external source of power were available, shall be operable.
5.
A maximum of one drywell spray loop may be inoperable for 30 days when reactor water temperature is greater than 212*F.
6.
If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the COLD SHUTDOWN or REFUEL condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, rr Millstone Unit 1 3/4 5-1 Amendment No. 4, 31
C:MITING CONDITION FOR OPERATION 4'
3.5 CORE AND CONTAINMENT COOLING SYSTEMS E.
Cont ainment Coolina Svbsystems 1.
Except as specified 3.5.B.2, 3.5.B.3, 3.5.F.6, and 3.5.F.7, l
both containment cooling subsystems shall be operable whenever irradiated fuel is in the reactor vessel.
2.
From and after the date that one of the emergency service water (ESW) subsystem pumps is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding thirty days unless pump is sooner made operable, provided that during such thirty days all other active components of the containment cooling system are operable.
3.
From and after the date that one active component in each containment cooling subsystem or a LPCI and ESW in one containment cooling subsystem is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding 7 days provided the remaining active components in each containment cooling subsystem, both core spray subsystems and both emergency power sources for operation of such components, if no external source of power were available, shall be operable.
4.
From and after the date that one LPCI and one ESW pump in each containment cooling subsystem is made or found to be inoperable for any reas.on, reactor operation is permissible only during the succeeding four days provided the remaining active components of the containment cooling subsystems, both core spray subsystems and both emergency power sources for operation of such componcnts, if no external source of power were available, shall be operable.
5.
From and after the date that one containment cooling subsystem is made or found to be inoperable for any reason, reactor. operation is permissible only during the succeeding four days provided that all active components of the other containment cooling subsystem, both core spray subsystems and both emergency power sources for operation of such components, if no external source of power were available, shall be operable.
6.
If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I Millstone Unit 1 3/4 5-3 Amendment No. I, 31 lL_-_______--___
2 L'IMITING C0f!DIT10N FOR OPERATION 2.5 CORE AND CONTAINMENT COOLING SYSTEMS T.
-Minimum Core and Containment Coolina System Availability
.I.
Except as specified in 3.5.F.2, 3.5.F.3, and 3.5.F.7 below, l
both emergency power sources shall be operable whenever irradiated fuel is in the reactor.
2.
From and after the date that the diesel generator is made or found to be inoperable, for any reason, continued reactor operation is permissible only during the succeeding seven days provided that the gas turbine generator, FWCI, Autnmatic Pressure Relief Subsystem, all components of the low pressure core cooling and the containment cooling subsystems shall be operable.
3.
From and after the date that the gas turbine generator is made or found to be inoperable, for any reason, continued reactor operation is permissible only during the succeeding four days provided 'that the diesel generator, all components of the APR subsystem, all components of the low pressure core cooling and the containment -
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cooling subsystems shall be operable.
4.
If the requirements of 3.5.F.1 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SHUTDOWN or.
REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
Any combination of inoperable components in the core and containment cooling. systems shall not defeat the capability of the remaining operable components to fulfill the core and containment cooling functions.
6.
Except.as specified in 3.5.F.7, when irradiated fuel is in the vessel and the reactor is in the COLD SHUTDOWN CONDITION all low pressure core and containment cooling subsystems may be inoperable provided that no work is being done which has the potential for draining the reactor vessel.
SURVEILLANCE REQUIREMENT 4.5 CORE AND CONTAINMENT COOLING SYSTEMS F.
Surveillance of Core and Containment Coolina System 1.
The surveillance requirements for normal operation are in Section 4.9.
I Millstone Unit 1 3/4 5-8 Amendment No. 1,31 l
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. j :"' TUG C001 TION FOR OPERATION 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 2.5.F.7.
When irradiated fuel is in the reactor vessel and the reactor is in
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the REFUEL CONDITION, a single control rod may be withdrawn and the drive mechanism replaced or fuel removal and replacement. may be conducted provided that the following conditions are satisfied.
.(a)
The reactor vessel head is removed.
-(b) The cavity is flooded.
(c) The spent fuel pool gates are removed.
(d). Water level is maintained within the limits of-
-Specification 3.10.C.
(e)
For one of the following combinations of ECCS subsystems, power to one of the subsystems listed for that combination shall be.
supplied by 4160 volt bus 14E and power to the other subsystem shall be supplied by bus 14F:
(i) both core spray subsystems (ii) both trains of the low pressure coolant injection (LPCI) system.
(iii) one core spray subsystem and. one train of the LPCI system.
Both buses 14E and 14F shall be capable of being supplied by separate power sources as specified in paragraph 3.7.B.4.
The ECCS subsystems for the selected combination shall be operable or available for operation with the respective 4160 volt supply breaker'('s) for the pumps racked down.
(f) With the torus drained, (1) the ECCS configuration required in 3.5.F.7(e) shall be aligned with the condensate storage tank and the condensate storage. tank' suction valve V7-58 locked open, (ii) the condensate storage tank shall contain at least 414,000 gallons of usable water, i
(g)
The minimum electrical power source requirements shall be I
the same as specified in paragraph 3.7.B.4.
(h)
No work will be performed in the reactor vessel other than fuel sipping while a control rod drive housing is open.
i (i)
Fuel removal and replacement will not be done without a full l
complement of control rods.
(j)
During fuel movement, no work being done which has the potential for draining the vessel.
(k)
For purposes of control rod drive mechanism removal and/or replacement, specifications 3.5.F.7(a), (b) and (c) do not apply provided ECCS systems identified in 3.5.F.7(e) are operable with the 4,160 volt supply breaker (s) racked in.
l Millstone Unit 1 3/4 5-9 AmendmentNo.J,J/,31
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t Z?TINGCOC'TIONFOROPERATION 3.~
CONTAINMENT SYSTEMS 3.7.E.3.
From and after the date that one circuit of the standby gas treatment system is made or found to be inoperable, for any reason, reactor operation and fuel handling is permissible only during the succeeding seven days unless such circuit is sooner made operable, provided that during such seven days all active components of the other standby gas treatment circuit shall be operable.
4 During fuel handling, both circuits of the standby gas treatment system shall be operable, except as stated in paragraph 3.7.B.3.
In
. addition, there siall be operable either (a) two sources of offsite power (two 345KV or one 27.6KV and one 345KV) and one emergency power source, or (b)'one source of offsite power (345KV or 27.6KV)
.and two emergency power sources to operate components required in paragraph 3.7.B.3.
5.
If the above cannot be
- met, procedures shall~ be initiated immediately to establish the conditions listed in 3.7.C.I.a and b l
and compliance shall be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.
6.
Primary containment shall be purged through the standby gas treatment system at all times when primary containment integrity is required.
SURVEILLANCE REQUIREMENTS At leas't'once per operating cycle, automatic initiation of each 4.7.B.3.
a.
branch of the standby gas treatment system shall be demonstrated.
b.
At least once per operating cycle, manual operability of the bypass valve for filter cooling shall be demonstrated, c.
When one circuit of the standby gas treatment system becomes inoperable, the other circuit shall be demonstrated to be operable immediately and daily thereafter.
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