ML20150F667
| ML20150F667 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/28/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20150F670 | List: |
| References | |
| TAC 66954, TAC 67040, DPR-65-A-127 NUDOCS 8804050320 | |
| Download: ML20150F667 (9) | |
Text
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e nsay'o UNITED STATES
- 1 NUCLEAR REGULATORY COMMISSION wAsm NG TON, D. C. 20555
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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
00CKETkJ1.,50_-336 FILLSTONE NUCLEAR P0hER STATION, UNIT NO. 2 APEh0 PENT TO FAClll1Y OPERATING LICENSE Amendment No.127 License No. DPP-65 1.
The Nuclear Regulatory Contrission (the Conmission) has found that:
A.
The applications for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated Cecember 23, 1987 and February 3,1988, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cornission'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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this anendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliarce with the Comission's regulations; C.
The issuance of this atendn.ent will ret be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this an>endnent is in eccordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is aterded by changes to the Technicel Specifications as indicated in the attachnent to this license anendeent.
I and paragraph 2.C (2) of Facility Operating License No. CFR-65 is hertby arended to read cs fo11cws:
(2) Technical Speciff_ cations The Technical Specifications contained in Appendix A, as' revised through Aniendment No. 127. are hereby incorporated in the license.
The licensee shall crerate the facility in accordance with the Technical Specifications.
3.
This license ar.endnent is effective as cf the date of its issuance.
F HE NUCLEAR ULAT RY COMMISSION i
C Stolz, Director J n P of ct Directorate I-4 Division of Reactor Frojects I/II Office of Nuclear Peactor Regulation Attachnent Changes to the Technical J
Specificaticos Cate of Issuance: March 28, 1988 i
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ATTACHMENT TO LICENSE AMEh0 MENT h0.127 i
i FA C l _L,T IJ,,0,P,E,RA,TJ,N,G,,L I C E N S E,,NOL., 0 P R - 65 CCCKET N0. 50-336 i
Replace the following pages of the Appendix A Technical Specifications with i
i the enclosed pages.
The revised pages are identified by atendment number and l
contain vertical lines indicating the areas of change. The correspending osorleaf rages are provided te maintain dccunent coripleteness.
Remove Insert f
i 3/4 3-42 3/4 3-42 i
3/4 9-15 3/4 9-15 B3/4 3-4 B3/4 3-4 l
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h TABLE 4.3-6 r-REMOTE SHlfTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 7
CHANNEL CHANNEL INSTRUMENT CilECK CALIBRATION cz3 1.
Wide Range Logarithmic M
N.A.
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Neutron Flux 2.
Reactor Trip Breaker Indication M
N.A.
3.
Reactor Cold Leg Temperature M
R 4.
Pressurizer Pressure a.
Low Range M
R w
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High Range M
R (se E
5.
Pressurizer Level M
R 6.
Steam Generator Level M
R 7.
Steam Generatot 'ressure M
R s
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Millstone - Unit 2 3/4 3-42 Amendment No. 49, 100, 127 s
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TABLE 3.9-1 l
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ACCESS DOORS TO SPENT FUEL POOL AREA
'l Door No.
Elevation
_Lecation Type Area Serviced i
3 i
291 14'6" M.7-13.5 Double Door SFP Skimmer System L
292 or 14'6" R/S-13.9 Double Door Solidification System j
207 or 8' Rollup, Door 293 14'6" Q/R-13.0 Double Door Maintenance Shop 20S 14'6" S-13.9 16' Rollup Railway Access Door f
294 14'6" Q-20.7 Single Door D/G Room 295 3S'6" F.8-13 8' Rollup Aux. & R. W. HVAC i
Door i
296 38'6" F.8 18.5 Single Door Aux. & R. W. HVAC i
297 38'6" F.8-13.5 Single Door North Stairwell i
38'6" H.4-18.9 Double Sliding Elevator i
Door j
298 38'6" M.4-13.9 Single Door Penetration Room i
299 3S'6" M.7-18.9 Double Door Main Exh. Fan Room a
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247 38'6" M.7-17.2 Single Door South Stairwell f
j 254 55'6" S-17.2 Single Door Roof Above Storage Floor f
t 3
253 25'6" S-13.9 Single Door Roof Above F. O. Tanks 274 38'6" R-17.2 Single Door Area below Mezzanine l
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MILLSTONE - UNIT 2 Amendment if. 127 3/4 9-15 s
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REFWLING OPERATIONS,
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$?0 RAGE POOL AREA VENTILATION SYSTEM - FUEL STORAGE l
i LIMITING CONDITION FOR OPERATION 3
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' 3.9.15 At least one Enclosure Building Filtration System shall be 0PERABLE and capable of automatically initiating operation in the.auxil-1 l
iary exhaust mode and exhausting through HEPA' filters and charcoal adsorbers on a storage pool area high radiation signal.
1 APPQCABILITY: WHENEVER IRRADIATED FUEL IS IN THE STORAGE POOL.
ACTION:
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.' With the requirements:of the above specification not satisfied, suspend all
. operations involving movement of fuel within the storage pool or crane J
- operation with loads over the storage pool until at least one spent fuel l
storage pool ventilation system is restored to OPERABLE status.
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i SURVEILLANCE REQUIRs.MEjf75
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4.9.15 The above required Enclosure Building Filtration System shall be demonstrated OPERABLE:
1 a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating.
j from the control room, flow through the HEPA filters and charcoal a'dsorbers and verifying that the system operates for at least r
j 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.
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At least once per 18 mcmths or (1) after any structural maintenance' 1
on the HEPA filter or charcoal adsorber housing's, or (2) following painting, fire or chemical release in any ve.ntilation :ene communi-cating with the system by:
J MILLSTONE - UNIT 2 3/4 9-16.
. Amendment No. 7e 4
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INSTRUMENTAT!0h i
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3/4.3.3.2 INCORE DETECTORS l
The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurments ontained from use of this system accurately represent the spatial neutron flux distribution of tV reactor core.
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3/4.3.3.3 SEISMIC INSTRUMENTATION l
i The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is svailable to promptly determine the segnitude of a seismic event and evaluate the response of those features important to safety. This capability is recuired to pemit comparison of the measured response to,that used in the design basis for the facility.
5 3/4.3.3.4. METEOROLOGICAL INSTRUMENTATION i
The OPERABILITY of the meteorological instrumentation ensures that i
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sufficient meteorological data is available for estinating potential 4
radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is i
required to evaluate the need for initiating protective measures to i
protect the health and safety of the public. This instrumentation is I
j consistent with the rocceendations of Regulatory Guide 1.23 "Onsite
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l Meteorological Programs."
I 3/4.3.3.5 REMOTE SHl#DOWN INSTRUl(NTATION The OPEPABILITY of the reacte shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room.
i This capability is required in the event control room habitability _is lost and is consistent with General Design Criteria 19 of 10 CFR H.
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MILLSTONE - UNIT 2 8 3/4 3-3 Amendment
. 25.49 i
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INSTRUMENTATION 3/4.3.3.6 Fire Detection Instrumentation j
OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires vill reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to 1
provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
t S/4.3.3.7 Accident Monitoring Instrumentation 1-I The OPERABILITY of the accident monitoring instrumentation ensures tvP sufficient informa:lon is available on selected plant parameters to monitor and assess these variables during and following an accident.
This capability is consistent with the recommendations of NUREG-0578, "TM1-2 Lessons Learned i
Task Force Status Report and Short-Term Recommendations".
l Millstone - Unit 2 B3/4 3-4 Amendment 35,4, 66, 3 0, 127 s
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