ML20043H655
| ML20043H655 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/12/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Connecticut Light & Power Co, Northeast Nuclear Energy Co (NNECO), Western Massachusetts Electric Co |
| Shared Package | |
| ML20043H656 | List: |
| References | |
| DPR-65-A-145 NUDOCS 9006260252 | |
| Download: ML20043H655 (9) | |
Text
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NORTHEAST NUCLEAR ENERGY C0ftPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 HILLSTONENUCLEARPOWERSTATION,UtqT_NO._2, AMENDMENT TO FACILITY OPERATING LICENSE 1
Amen 6ent No.145 License No. DPR-65 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The app (lication for amendment by Northeast Nuclear Energy Company, et al.
the licensee), dated March 21, 1989 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; B.
The facility will operate in corformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amerdrent will not be inimical to the comon defense and security or to the health and iafety of the public; cnd r
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Commission's regulations and all applicable requirements have been satisfied, l
I 9006260232 900612 DR ADOCK 0500 6
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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. OPR-65 is hereby amended to read as follows:
c (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.145, 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 I
implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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h F. Stolz, Directorj f
ject Directorate 1-4 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 12, 1990 J
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4 ATTACHMENT TO LICENSE AMENDMENT NO.145 i
FACILITY OPERATING LICENSE N0. DPR-65 f
i DOCKET N0. 50-336 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. The corresponding overleaf pages are provided to maintain document completeness.
Remove Insert YIII Yll!
XIll Xill l
3/4 7-42 B 3/4 7-7 8 3/4 7-7 l
l 1
5
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1!!E.E l
l l
LIMITING CONDIT!0NS FOR OPERATION AND SURYt!LLANCE REQUIREMENTS i
HEI911
- EE l
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTA!!0Wif..................................
3/4 6-1 j
Contai nment Integri ty................................
3/4 6-1 Containment Leakage..................................
3/4 6-2 Conta i nment Ai r Locks................................
3/4 6-6 Internal Pressure....................................
3/4 6-8 A t r.Tempe r a ture......................................
3/4 6-g I
containment Structural Integri ty.....................
3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEM 5.................
3/4 6-12 l
Containment Spray Systas.............................
'3/4 6-12 Containment Ai r Reci rculation System............"..'...
3/4 6 3/4.6.3 CONTA!NMENT ISOLATION VALYt5.........................
3/4 6-15 3/4.6.4 Col #UST!8LE GAS C0NTROL..............................
3/4 6-20
)
Hydrogen Analyzers...................................
3/4 6-20 l
El ectric Hydrogen Recos61 ners - 1..... :............
3/4 6-21 l
Hydrogen Purge 5ysten................................
3/4 6-13 Post-!ncident Reci rculation Systems..................
3/4 6-24 3/4.6.5 SECONDARY C0NTA!!#ENT................................
3/4 6-25 l
Encl osu're Bui l di ng Fil trati on System.................
3/4 6-25 l
Enclosure Building Integrity.........................
3/4 6-28 l
l 1
MILLSTONE - UNIT 2 VII Amendment No. 104 l
6 A
m
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LIMITING CONDITIONS FOR OPERATION AND SURVflLLANCE RE0UIREMENTS SECTION Egd 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..........................................
3/4 7 1 S a fe ty V a l v e s..........................................
3/4 7 1 Auxiliary Feedwater Pumps..............................
3/4 7 4 Condensate Storage Tank................................
3/4 7 6 Activity...............................................
3/4 7 7 Main Steani Line Isolation Valves.......................
3/4 7 9 I
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........
3/4 7-10 l
3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM...........
3/4 7 11 l
3/4.7.4 SERVICE WATER SYSTEM...................................
3/4 7-12 v4.7.5 rt00D u vet............................................
u 713 i
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..............
3/4 7 16 3/4.7.7 SEALED SOURCE CONTAMINATION............................
3/4 7 19 3/4.7.8 SNUBBERS.......................................'........
3/4 7 21 3/4.7.9 FIRE SUPPRESSION SYSTEMS...............................
3/4 7-33 Fire Suppression Water System..........................
3/4 7-33 Spray and/or Sprinkler Systems.........................
3/4 7 37 Fire Hose Stations.....................................
3/4 7 39 3/4.7.10 PENETRATION FIRE BARRIERS..............................
3/4741 3/4.7.11 ULTIMATE HEAT SINK.....................................
3/4 7-42 l
l 1
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES...........................................
3/4 8-1 Operating..............................................
3/4 8-1 Shutdown...............................................
3/4 8 5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS......................
3/4 8 6 A.C. Distribution - Operating..........................
3/4 8 6 A.C. Distribution - Shutdown...........................
3/4 8 7 D.C. Distribution Operating..........................
3/4 8 8 D.C. Distribution - Shutdown...........................
3/4 8-10 MILLSTONE - UNIT 2 VI!!
Amendment No. 77, #, #, #f 145
IliDG BASES SECTION EAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE........................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........ B 3/4 7-3 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM........... B 3/4 7 3 3/4.7.4 SERVICE WATER SYSTEM................................... B 3/4 7 4 3/4.7.5 FLOOD LEVEL............................................ B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.............. B 3/4 7 4 3/4.7.7 SEALED SOURCE CONTAMINATION............................ B 3/4 7-5 3/4.7.8 SNUBBERS............................................... B 3/4 7 5 3/4.7.9 FIRE SUPPRESSION SYSTEMS............................... B 3/4 7 6 3/4.7.10 PENETRATION FIRE BARRIERS.............................. B 3/4 7-7 3/4.7.11 ULTIMATE HEAT SINK..................................... B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS.................................. B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................... B 3/4 9 1 3/4.9.2 INSTRUMENTATION........................................ B 3/4 9 1 3/4.9.3 DECAY TIME............................................. B 3/4 9-1 3/4.9.4 CONAINMENT PENETRATIONS................................ B 3/4 9 1 3/4.9.5 C OPMUN I CAT I ON S......................................... B 3/ 4 9 - 1 3/4.9.6 CRANE OPERABILITY-CONTAINMENT BUILDING................ B 3/4 9-2 3/4.9.7 CRANE TRAVEL--SPENT FUEL STORAGE BUILDING.............. B 3/4 9 2 3/4.9.8 SHUTDOWN COOLING AND COOLING RECIRCULATION............. B 3/4 9 2 l
1 MILLSTONE - UNIT 2 XIll AmendmentNo.77,M,Q,M,$f
- 145,
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.LEEE BASES SECTION pag [,
3/4.9,9 AND 3/4.9.10 CONTAINMENT AND RADIATION MONITORING AN CONTAINMENT PURGE VALVE ISOLATION SYSTEM.......
...... B 3/4 9-2 3/4.9.11 AND 3/4.9.12 WATER LEVEL - REACTOR V STORAGE POOL WATER LEVEL............ESSEL AND
.................... 8 3/4 9-2 i
3/4.9.13 STORAGE POOL AADIATION MONIT0 RING.......................
3 3/4 9-3 3/4.9.14 AND 3/4.9.15 STORAGE P00L AREA VENTILATION SYSTEM.......
3/4.9.16 SHIELDED CASK............................................ B 3/4 9-3 3/4.9.17 MOVEMENT OF FUEL OVER REGION !! RACKS..........
l 3/4.9.18 SPENT FUEL P00L.........................................
8 3/4 9-3 l
3/4.9.19 i"
SPENT FUEL P00L.........................................
8 3/4 9-4 l.
3/4.10 SPECIAL TEST EXCEPTIONS 4
3/4.10.1 SHUTDOWN MARGIN.................................
.3/4.10.2 GROUP HEIGHT AND INSERTIONLIMITS........................ 83/410-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITAT CRITICALITY................. ION - REACTOR i
8 3/4 10 i t
3/4.10.4 PHYSICS TESTS............................................ B 3/4 10-1 3/4.10.5 CENTER CEA MISALIGNMENT.................................. 83/410-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS......................................... B 3/4 11-1
!3/4.11.2 GASEOUS EFFLUENTS...................................
3/4.11.3 TOTAL 00$E............................................... B 3/4 11-4 MILLSTONE - UNIT 2 XIV Amendment No pp,Jpp,Jpp, 117 9
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PLANT SYSTEMS 3/4.7-11 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION i
3.7.11 The ultimate heat sink shall be OPERABLE with an average water temperature of less than or equal to 75'F at the Unit 2 intake structure.
APPLICABILITY: MODES 1, 2, 3, AND 4 KI1M:
With the requirements of the above specification not satisfied, be in at least HOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
$URVEILLANCE REQUIREMENTS 4.7.11 The ultimate heat sink shall be determined OPERABLE:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature at the Unit 2 intake structure to be within limits, b.
At least once per 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> by verifying the average water temperature at the Unit 2 intake structure to be within limits when the average water temperature exceeds 70*F.
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l MILLSTONE UNIT 2 3/4 7-42 Amendment No. 145
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a PLANT SYSTEMS BASES suppression system consists of the water system, spray and/or sprinklers and fire hose stations. The collective capability of the fire suppression systems t
is adequate to minimize potential damage to safety related equipment and is a 1
major element in the facility fire protection program, In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
l In the event the fire suppression water system becomes inoperable, Immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
The requirement for a
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twenty four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3.4.7.10 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that
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fires will be confined or adequately retarded from spreading to adjacent portions of the facility.
This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.
During period of time when a barrier is not functional, alternate measures are taken to prevent the possible spread of fire.
These measures include verifying the operability of fire detection or suppression systems on ha.th sides of the affected barrier and establishing a fire watch patrol, or posting a continuous fire watch in the vicinity of the affected barrier, or installation of a temporary fire stop pending restoration of the permanent' I
seal.
3/4.7.11 ULTIMATE HEAT SINK l
The limitations on the ultimate heat sink temperature ensure that sufficient l
cooling capacity is available to either, l
1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The. limitations on muimum temperature are based on a 30 day cooling water supply to safety r'., lated equipment without exceeding their design basis temperature.
MILLSTONE - UNIT 2 B 3/4 7-7 Amendment No. 145
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