ML20050C667
| ML20050C667 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/02/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20050C664 | List: |
| References | |
| NUDOCS 8204090228 | |
| Download: ML20050C667 (14) | |
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NUCLEAR REGULATORY COMMISSION g,
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1 THE CONF 1ECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY
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WESTERN MASSACHUSETTS ELECTRIC COMPANY AND NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NOCLEAR POWER STATION, UhlT 1 s
AMENDMENTTOPR0'VESIONALOPERATINGLICENSE g,...
Amendment No. 83 License No. DPR-21 1.
The Nuclear Regulatory Commission (t'he Commission) has found that:
A.
The application for amendment by the Connecticut Light and Power Company, the Hartford Electric Light Company, Western Massachusetts Elqctric Company'and Northeast Nuclear Electric Company (the licensees) dated March 9, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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;
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Thereisreasonableashurance(5)thattheactivitiesauthorizedby C.
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 th'is amendment will not be inimical to the common defense and security of to the health and safety of the public; and E.
The issuance of tFis amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8204090228 820402 PDR ADOCK 05000245 P
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-21 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A -
and B as revised through Amendment No. 83, are hereby 2
incorporated in t,he license. Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications.,
, i 3.
This license amendment. is' effective on its date of-issuance.
- r-3 FOR THE NUCLEAR REGULATORY COMMI5SION D
ch Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 2,1982 e
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d ATTACHMENT TO LICENSE AMENDMENT NO. 83 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages.of Appendix A Technical Specifications with the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the area of change.
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PAGES
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- 3/4 12-3
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i i3/4 12-5 g
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3/4 12-7 3/4 12-9 1 '
3/4 12-9a 3/412-9b(new) 3/4 12-10 3/4 12-11 3/4 12-11a (new) 3/4 12-12 6-21t*
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0, LIMITING CONDITION FOR OPERATION
. SURVEILLANCE Rl'QUIRDIENTS 4.
If 3.a above cannot be fulfilled, place the g.
The fire pump diesel engine shall be reactor in llot Standby within the,next 6 hpurs demonstrated OPERAlli.E:
and in Cold Shutdown within the fo,11owing twenty-four (24) hours.
i-1.
At least once per 31 days by veri '
fying:
(a) The fuel storage tank contains at least 125 gallons of fuel, and (b) The diesel starts from ambient conditions and operates for at least 20 minutes, i +
2.
At least once per 92 days by verify-ing that a sample of diesel fuel
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from the fuel storage tank, obtained in accordance with ASTH-D270-65, is within the acceptable limits specified' rs ',
in Tabic 1 of ASTH-D975-74.with re-j spect to viscosity, water pontent
[a and sediment.
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g 3.
At least once per 18 months by:
l (a)
Subjecting the diesel to an in-spection in accordance with procedures prepared in conjunc-tion with its manufacturer's recommendations for the* class of service, and e
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o' Amendment t. (J, 83 t
3/4 12-3 h
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 11 Spray and/or Sprinkler Systems B. Spray and/or Sprinkler Systems 1.
The following spray and/or sprinkler systems 1.
Each of the spray / sprinkler systems in 3.12.B located in the following areas shall be op-shall be demonstrated OPERABLE:
erable at all times when equipment in the area is required to be operable:
a.
At least once per 12 months by cycling each testable valve in the flow path through at a.
Diesel Generator Room - manually operated least ene complete cycle of full travel, b.
Diesel Generator Day Tank' Room b.
At least once per 18 months:
c.
Hydrogea Seal Oil Unit 1.
By performing a system functional test which includes simulated automatic d.
Cas Turbine Building - manually operated actuation of the system, and:
e.
Condenser Bay (a)
Verifying that the automatic valves in the flow path actuate to their f.
Turbine Lubrication - Oil Room Deluge correct positions on a simulated test signal, and g.
Boiler Room and Machi'n khop-wetpipe I
(b)
Cycling each valve in the' flow path l
that is not testabic during plant
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operation (except valve 1-F-71) h.
Bearing Lift Pump and Seal Oil through at least one complete cycle Detraining Tank
- wet pipe.
of full travel and 1.
Reactor Building 14'-6" Elevation - wet pipe 2.
By inspection of the spray headers to verify their integrity, and 2.
With one or more of the above required spray, and/or sprinkler systems inoperable, establish 3.
By inspection of each nozzle to verify a continuous fire watch with backup fire suppres-no blockage.
sion equipment for the unprotected area (s) within I hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report re-quired by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days out-lining the action taken,'the.cause of the inop-erability and the plans and schedule for restor-ing the system to OPERABLE status.
Amen-3 ment No. 44, 53, 83 3/4 12-5
a LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS Carbon Dioxide and llalon 1301 Systems C.
Carbon Dioxide and Italon 1301 Systems 1.
The following high pressure CO systems shall 1.
Each of the high pressure CQ,, systems in 3.12.C.1 2
be OPERABLE with the storage tanks at least 90%
shall be demonstrated OPERABLE:
of full charge weight whenever equipment in the high pressure CO,, protected areas is required a.
At least once per 6 months by verifying CO.,
to be OPERABLE. '
storage tank weight.
a.
Cas Turbine Enclosure, b.
At least once per 18 months by:
2.
With one or more of the above required high pres-1.
Verifying the system, including associated sure CO systems inoperable, establish a contin-ventilation dampers, actuates manually 2
uous fire watch with backup flutsuppression equip-and automatically, upon receipt of a ment for the unprotected area (s) within I hour; simulated test signal, and restore the system to OPERABLE status within 14 days or, in lieu of any other report required 2.
Performance of a flow test through head-ers and nozzles to assure no blockare.
by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days out.
lining the action taken, the cause of the inop-erability and the plans and adh8dyle for restor-2.
The llalon 1301 System referenced in 3.12.C.3 ing the system to OPERAB status-shall be demonstrated OPERABLE:
'3.
The Halon 1301 System for the fire pump house a.
At least once per 6 months the weight shall be operable, with the bottles connected and pressure of the refillable container shall and available for service and the bottle at be. checked.
If the container shows a loss in 95% of full charge weight, net ueight of more than 5% or the pressure drops to 325 psig it shall be refilled or 4.
From and after the time the, fire pump house replaced.
Halon System is determined to be inoperable within one hour establish a continous fire b.
At least once per 18 months by verifying watch witti backup fire suppre'ssion equipment the system and associated ventilation dampers for the unprotected equipment and/or area ;
sctuate automatically and manually to a simu-lated actuation signal. A visual inspection restore the system to OPERABLE status within 14 scharge m W s to ass e no W c W days or, in lieu of any other report required sha n W pe h m d by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days out+;
lining the action taken,.the cause of the inop
erability and the plans and schedule for restor-ing the system to OPERABLE status.
Amenoment No. 44, 83 3/4 12-7 I
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' Table 3.12.1 Location of Hose Station linse Station No.
Location
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151 Inside Cable Vault-118 IIallway Near H. P.0ffice 110 i
Turbine' Bldg 1%'6" Reactor Feed Pu=p Area 112 Turbine Bldg 14'6" Reactor Feed Pump Area 105 Turbine Bldg 14'6" Outside D'iesel Room'
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I Turbine Bldg 14'6" Condensite Pump Area 103 TrbineBkdg14'6"CondensateBoosterPumpArea 111
,u.a 121 Turbine Bldg 34' North of Switchgear Area 120 Turbine Bldg 34' We'st of Switchgear Area, 125 Turbine Bldg 34' Outside Battery Rooms 113
, Reactor Bldg 14'6" North Wall by Stairway 114 Reactor Bldg 14'6" East Wall by Railway Access 115 Reactor Bldg 14'6" South Wall by CRD Pump Room Stairs 116 Reactor Bldg 14'6" East Wall Outside TIP Room 117 Reactor Bldg 14'6" South Wall Opposite S/D Pump Room 128 Reactor Bldg 42' Northeast Area by Stairway l
129 Reactor Bldg 42' East Wall by RBCCW HX 130 Reactor Bldg 42' by CU Pump Room 101 SE Warehouse, 14'6" l
102 SV Warehouse, 14'6" 103 W Machine Shop, 14'6" 104 Turb. Outside E Decontam. Room, 14'6" 106 Turb. Cond. at S Stairs, 11' 107 Turb. Cond. W Wall at Bypass Valves, 11' 109 Turb. Cond. E. Wall, 11'
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Amendment No. (4, 53, 83 3/4 12-9
Tcblo 3.12.1 Location of Hoce Station Hosa Station No.
Location 119 E. Wall Control Room, 36' 122 Turb. at Telephone Room, 34'
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Turb. Elevator,36'
-s 123 i
124 Turb. & keup Demineralizer, 34' 126
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H & V Room, 42' s
- l Rx. SW Corner, 42' 127
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131
- Turb.'S Wall, 54'
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Turb. U all S,54 '
132 2
Turb.'W Wall N, 54' 133 134 Turb. E Wall N,54' 135
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,Turb. E Wall C, 54'
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Turb. E Wall S, 54' 136
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H & V Room E Wall, 54' 138
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Rx. SW Corner, 65' 139 Rx. SE Stairs, 65'
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140 Rx. W Wall, 82' 141 Rx. E Wall on Cont., 82' 142 Rx. NW Corner, 108' 143 SW Corner, 108' 144 Rx. E Wall, 108' 145 Radwaste Control Board, l' 146 Radwaste Filters, l' 147 Radwaste Pump S, 20' 148 Rad.raste N. Wall, -17 '
149 Turb. at Elevator, 25' 150 Solid Radwaste NW Corner, 14'6" l
152 S611d.Radwaste SE Corner, 14'6" l
0 Amend =cnt No. 33, l
C,.
Tcble 3.12.1 Location of Hose Station Hosa Station No.
Location 161 Reactor Building 14'-6" Near Personnel Entry Drywell 162 Reactor Building 65'-6" Across From Hatchway 160 :
Turbine Building 14'-6" Hallway between Chem Lab and Computer Room
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I Amendment No. 83 3/4 12-9b 4
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS
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Fire Detection Instrumentation'.
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' Fire Detection' Instr'umentation 1.
The minimum required fire detection instrumenta-1.
Each of the fire detection. instruments listed tion for each fire detection zone shosn in Table.
in Table 3.12.2 shall be demonstrated OPERABLE 3.12.2 shall be OPERABLE whenever equipment in at 1 cast once per 6 months by performance of an that fire detection zone is required to be INQTRUMENT FUNCTIONAL TEST with the exception OPERABLE.
that the function.a1 test ney consist of inject-Ing a simulated electrical signal into the seas-l 2.
With less than the minimum required number of the urement', channel.rather than the instrument, fire detection instrument (s) shown in Table 3.12.2 OPERABLE:
2.
The-non-supervised circuits between the above required detection instruments and the control a.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a watch patrol room shall:be dbmonstrated OPERABLE at 1 cast to inspect the zone (s) with the inop-once pe( $1~ddys;per approved procedures.
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crable instrument (s) at least once per l ",,
hour, and 7
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b.
Restore the inoperable instrument (s) to i-OPERABLE status within 14 days or, in lieu of any other report required by Soe:afication 6.9.1, prepare and sub-mit a Special Report to the Commission pursuant to Specification 6.9.-2 within- -
the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restor-i ing the instrument (s) to OPERABLE status.
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't Amendment No. 44, 14 12-1p a
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e Tchla 3.12.2 Fire Detection Instruments NOTE: No 'two (2) adjacent detectors inoperable.
HEAT SMOKE l
MINIMLH MINIgg; TOTAL INSTRLMENTS TOTAL INSTRLYENTS INSTRUMENT LOCATION AVAILABEE REQUIRED AVAILABLE REQUIRED 1.
Cable Vault 15 12
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2.
U2 Seal Oil Unit 1
1 3.
Condenser Bay
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36
'25 4.
Diesel Generator Room 3
s
,3 2
-s.,
5.
D/G Fuel-Oil Day Tank Room 1
1 jl*
6.
G n Turbine Enclo,sure, 6
4 7.
Rx Bldg (1-FDS-1) a.
R-2a Rx Bldg 14 '6" 7
5 N.W. Corner Including Crd Bank b.
R-2B Rx Bldg 14 '6" N.E. Corner 4
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c.
R-2C_'Rx Bldg 14'6" S.E. Corner '
3 2_
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R-2D Rx Bldg 14'6" S,W. Corner 3
2 including C'.R.D. Ba'nk 1
1 e.
E-3 Tip Room f.
R-5 Shutdown Cooling Pump Room 1
1 8.
Rx Bldg (42' elev) 1-FDS-2 3
2 c.
R-17 C. lean-up Pump Room b.
R-18 Shut Down Heat Exchanger. Room 1
1 R-19 Rx Bldg 42' N.W. Corner to SE Corner 9
7 c.
9.
Rx Bldg (Elev. 65' and 82') 1-FDS-3 c.
R-12 Rx Bldg Elev. 65' 9
7 except gated area along North Wall' b.
R-13 Rx Bldg (Elev. 82") West Side 3
2 c.
R-14 Rx Bldg Elev. 82' East Side 2
1 10.
Turbine Bldg (14'-6") 1-FDS-4 c.
T-5A Condensate Pumps and Condensate Booster Pumps 6
4 b.
Condensate Demin Panel, Rx Feed Pumps 6
4 c.
T-SC TBCCW to Stator Cooling Unit 15 12 d.
T-6 Decon Room 1
1 e.
T-12 Chem Lab 3
2 f.
T-17 Mezzanine Above MCC D-2 (lA-2,)
3 2
Amendment No. 4J, 83 3/4 12-11 l
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Tablo 3.12.2 Fire Detection Instruments NOTE: No two (2) adjacent detectors inoperable.
HEAT SMOKE MINI:01 NIN1 HUM TOTAL INSTRUMENTS T.0TAL INSTRUMENTS INSTRUMENT LOCATION AVAILAET.E REQUIRED AVAILABLE REQUIRED RI.
Rad. Waste 1-FDS-5 c.
RW-A Radvaste Storage Bldg.
3 2
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b.
RW-B[LiquidRadwasteBldg.
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6' 4
- 62. Turb Bldg. (Elev. 36 '-6". 7 ' 34 '-6)[ 1-FDS-6
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T-19A Make Up Demin Storage Tk, MaWUp Demin'~.
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12 Ultra Filter, RP MG-Sets, Vital AC MG '~
, J ", 'f Sets, 4KV Bus 14E &,480V_ Bus J. 2E j f ' ;j;,,, :"f
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b.
T-19B 4KV Bus 14F and 480V Bus 12F 1
1 c.
T-19C 4KV Bus itA, 4KV Bus 14C and 480V MCC's ES & FS-3 2
d.
T-19D 4KV Bus 14B & 4KV Bus 14D 3
2 e.
T-19E 4KV* Bus 14G, DC Buses 101A & 101B. _
,8-6.*
480V Buses 12C & 12D, Iso Phase Bus Duct, f.
T-15A H 6 V Equipment.Rm Elev. 54'-6' 2
1 i3.
Control Room T-21 (Elev. 36'-6")
9 7
4.
Screen House SH 7
5 5.
Battery Rooms Station No. 2 I
c.
Battery Rm. 1 (Sta. #2) 1 1
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Battery Rm.* 1A (Sta. #2) 1 1
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Amendment No. 83 3/4 12-11a
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREliENTS' F.
All penetration fire barriers (including cabic 1.
Penetration fire barriers shall be verified penetration fire barriers, fire doors, and fire to be functional:
dampers) which protect safety-related areas shall
. At Icast once per 18 months by a visual be functional whenever safety-related equipment a.
in the area is required to be operable.
inspection.
2.
With one or more of the above required b.
Prior to returning a penetration I-ire penetration fire barriers non-functional,
-barrier to functional status following within I hour establish a temporary fire repairs or maintenance by performance barrier of equal ef f ectiveness or estab-of a visual inspection er the affected lish a continuous fire watch on at least penetration fire barrier (s).
one side of the affected penetration.
Restore the fire barrier (s) to functional i[
status within 30 days or, in lieu of any other report required by Specification 6.9.1, prepara and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the fire barrier (s) being non-functional and the plans and schedule for restoring the fire barrier (s) to functional status.
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l Amendment No. 44, 83 3/4 12-12 e
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ADMINISTRATIVE CONTROLS 1
THIRTY-DAY WRITTEN REPORTS (Continued) completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by addi-tional narrative material to provide complete explanation of the circum-stances surrounding the event;,.
Reactor' protection system or engineered safety features instrument a.
settings which are found to be'less conservative than those estab-
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11shed by the technicaf specifications but which do not prevent the fulfil.1 ment of the functiona.1 requirements of affected systems b.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by
- a limiting condition for operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls'which threaten to cause reduction of degree of. redundancy provided in reactor protection systems or engineered sa fety. features systems.
d.
Abnormal degradation of systems other than those specified in 6.9.1 8.c. above, designed to contain radioactive material resulting from th'e fission process.
SPECIAL REPORTS
.m 6.9.2 Spec'ial reports sha.11 be submitted to the Director of the Office of K
Inspection and Enforcement Regional Office within the time period specified for each report.
These reports shall be submitted covering the activities l
identified below pursuant to the requirements of the applicable reference I
spect fication:
In-service Inspection Results. Specification 4'.6.F.
a.
b.
Primary Containment Leak Rate Test Results. Specification 4.7.A.2.
c.
Secondary Containment Leak Rate Test Results. Specification 4.7.C.
"d.
Materials Radiation Surveillance Specimen Examination and Results, Speci fication 4.6.B.3.
e.
Fire detecticn instrumentation, Specification (3.12.E.2).
.f.
Fire suppression systems Speci,fications (3.12. A.2, 3.12.C.2, 3.12.C.2 and 3.12.C.4).
A=end=ent No. Id 43, 83 6-21
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