ML20033C423
| ML20033C423 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/10/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033C424 | List: |
| References | |
| NUDOCS 8112030172 | |
| Download: ML20033C423 (14) | |
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' %'j UNITED STATES 8
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20t55
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VERMONT YANKEE NUCLEAR POWER CORPCRATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. DPR-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated June 30, 1981-as supplemented August 26, 1981 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 Chaoter 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 67 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8112030172 811110 PDR ADOCK 05000271 P
2 1 3.
This license' amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Thomas A.
ppolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 10, 1981 s
l ATTACHMENT TO LICENSE AMENDMENT NO. 67 FACILITY OPERATING LICENSE NO. OPR-28
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DOCKET NO. 50-271 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 arer of change.
Remove Insert 11 ii iii iii iv-iv 187f 187f 1879 1879 187h 187h 1871 187i 187j 187k 1871 187m n-F
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5 TABLE CP' CONTENTS ' (Con' t)
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LIMITING CONDITIONS /OF OPERATICH - '
Page No.
SURVEILLANCE.
a s
s s
)
P.
Automatic Depressurization System 92 F'
- ~
-o s
'G.
'Reacto/ Core Isolation Cooling System (RCIC) 93-G f4' H.
Minimum Core and' Cont,ainment Cooling System Availability.
94
'H I
Maintenance of Filled Discharge Pipe 95
,I
, g 3.6 REACTOR COOLANT SYSTEM 105 4.6
'I A.
Pressure and Temperature Limitations 105 A-l l
B.
Coolant Chemistry...
106
.P.
B C.
Coolant Leakage.
108 C
D._
Safety and Relief Valves 108 D
E.
Structural Integrity 109 H
P.
Je t Pumps.
109 F:
G.
Single Loop Operation.
110 H.
Recirculation System 110 I.
Shock Suppressors.
110a I
J.
Thermal Hydraulic Stability.
110b.
J 3.7 STATIOrl CONTAINMENT SYSTEMS.
126
../
A.
126 A
B.
Standby Gas Treatment 130 u
C.
Secondary Containment System 131
.C D.
Primary Containment Isolation Valves 132 D
147 4.0 3.8 RADIOACTIVE EFFLUENTS A.
. Liquid Effluents 147 A
B.
' Radioactive Liquid Storage 149 B
C.
Gaseous Effluents.
149 C
3.9 RADIOACTIVE EFFLUENT MONITORING SYSTEMS.
161 4.9 A.
Liquid Effluent Monitoring System.
161 A
D.
Gaseous Ef fluent Monitoring Syst em 162 B
C.
Liquid Process Monitors.
164 C
D.
Radiological Monitoring Program 165 D
Amendment No. 67
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' TABLE OF CONTENTS -(Con' t) k cL R
3 LIMITING CONDITIONS OF OPERATION Page No.
SURVEILLANCE r+
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o 3.1 REACTOR PROTECTION SYSTEM.
18
...1 4.1 -
os
~4 3.2 - PROTECTIVE INSTRUMENT SYSTEMS.
32
- '4. 2
.i 3
A.
Emergency Core Cooling. System.
32 A
.H.
Primary Containment Isolation 33 B
' C.
Reactor Building. Ventilation Isolation and Standby Gas Treatment System Initiation 33 C
- 'D.
Air Ejector Off-Gas System Isolation 33 D
E.
Control Rod Block Actuation.
33 E
P.
Mechanical vacuum Pump Icolation 34 F
G..
Post-Accident Instrumentation.
34 G
'.H.
Drywell to Torus A P Instrumentation.
34 H
I.
Recirculaticn Pump' Trip Instrumentation.
34a
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I 68 4.3 3.3 - CONTROL ROD SYSTEM
-A.
. Reactivity Limitations 68 A
B.
69 B
C.
Scram Insertion Times 72 C
D.
Control Rod Accumulators 73 D
E.
Reactivity Anomalies 74 E
3.4 REACTOR STANDBY LIQUID CONTROL SYSTEM.
79 4.4 A.
bormal Operation 79 A-H.
Operation with Inoperable Components 80 B
. C.
Liquid Poison Tank - Doron Concentration 80 C-3.5 CORE AND CONTAINMENT COOLING SYSTEMS 85
' 4.' 5 A.
. Core Epray and Low Pressure Coolant Injection.
85 A
H.
Containment Spray Cooling Capability.
87 B
C.
Residual Heat' Removal (RHR) Service Water System 88 C
D.
Station Eervice Water and Al tern.4te Cooling Tower' Systems 89 D
E.
High Preseure Coolant Injcction (HPCI) System.
91 E
.m TABLE OF CONTENTS (O li't)
LIMITING CONDITIOt!S OP OPERATION Page No.
';tilWr. i t si.t.cE 3.10 AUXILI ARY ELECTRICAL POWER SYSTEMS 173 4.10 A.
Normal Operation ~.
173 A
B.
OI:eration with Inoperable Compcnents 176
'B C.
Diesel Fuel.........
177 C
3.11 REACTOR FUEL ASSEMBLIES.
180a
. ~.
'4.11 A.
Average Planar LHGR.
180a A
B.
LiiGR 180b B
C.
MCFR 180c C
3.12 REFUELING AND SPENT FUEL HANDLING.
181 4.12 A.
Refueling Interlocks 181 A
.B.
. Core Monitoring.
182 B
C.
Fuel Storage Pool Water Level 183 C
D.
' Control Rod and Control Rod Drive Maintenance.
184 D
E.
Extended Core Maintenance..
18 ".
E F.
Fuel Movement.
165 F
G.
Crane Operability.
185 G
H.
Spent Fuel Pool Water Temperatu e.
165a H
3.13 FIRE PHOTECTION SYSTEM 187b 4.13
-iv-Amendment No. [, 67
VYNPS-3 13 Limiting conditions for Operation 4.13 Surveillance Requirements C.
Fire Hose Stations C.
Fire Hose Stations 1.
Except as specified in 3.12.i;.2 below, all hose 1.
Each fire hose station snall be stations inside the Reactor fluilding, Turbine verified to be operable
. Building, and those inside the Administration Building which provided coverage of the Control a.
At least monthly by visual Room Building shall be operable V unever inspection of the station to assure equipment in the areas protected by the fire hose all equipment is available.
stations is required to be operable.
b.
At least once each 18 months by 2.
With one or more of the fire hose stations removing the hose for' inspection specified in 3.13.C.1 aoove inoperable, route an and replacing degraded coupling additional equivalent capacity fire hose to the gaskets and reracking.
unprotected area (s) from an operable hose station within one hour.
c.
At least once each year by hydro-stati'cally testing each outside hose at 250 lbs.
d.
At least once per 3 years by hydro-statically testing inside hose at 150 lbs.
e.
At least once per 3 years, partially open hose station valves to verify volvt ope.bility and no blockage.
i D.
High_ Pressure CO2 System D.
High Pressure CO2 System 1.
Except as specified in Specification 3.13.D.2, 1.
The CO2 system located in the cable the CO2 systems located in the cable vault, vault, switchgear room, and diesel fire switchgear room, and diesel lit e pta.ip day tank pump day tank tuou chul1 su rcom shall be operable, whenever equipment in the demonstrated operable.
area protected by the system is regiaired to be operable.
a.
At least once per six months by verifying each CO2 cylinder does not contain less than 901.of its initial charge.
Amendment No. $37., 67 le7-f
VINTS
-- 3.13 Limiting conditions for Operation 4.13 Surveillance Requirements 2.
From and af ter, the' date that the CO2 system in b.
At least once per 18 months by the cable vault or the switchgear room is verifying that the system, inoperable, establish a continuous fire watch including associated ventilation within one hour with backup f ire suppression dampers,willactuateautomaticallyg equipment. Restore the system to operable status to a simulated actuation signal, g
within 14 days or submit a report within the next 30 days to the Commission as specified in 6.7.C.2 c.
At least once per operating cycle a outlining the cause of inoperability and the flow path test shall be performed toverifyflowthrougheachnozzle.l plans for restoring the system t o operable status.
3.
From and after the date that the CO2 system in E.
Vital Fire Barrier Penetration Fire Seals the diesel fire pump day tank runn is inoperable, within one hour a fire watch shall be established 1.
Vital _ fire barrier penetration fire to inspect the location at least once every seals shall be verified to be hour.
Restore the system to operable status functional by visual inspection at
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within 14 days or submit a report within the next least once per operating cycle and 30 days.to'the Commission as specified in 6.7.C.2 following any repair.
outlining the cause of inoperability and the plans for restoring the system t o operable status.
4.13.F Sprinkler Systems E.
Vital Fire Barrier Penetration Fire Seals 1.
Each of the sprinkler systems specified 1.
Except as specified in Specification 3.13.E.2 in Table 3.13.F.1 shall be demonstrated below, vital fire barrier penetration seals
_ operable; pr otecting the Reactor Building, Control Room Building and Diesel Generator Rooms shall be a.
At least once per 12 months'bf intact.
cycling each tentable valve in the flow path throogt at least one 2.
From and after the date a vital fire barrier complete cycle of full travel.
penetration fire seal is not int act, a continuous fire watch shall be established on at least one b.
At least once each month by side of the affected penetration within I hour.
verifying each valve in the flow path is in its correct position.
3.13.F Sprintler Systems (For elect rie:al ly m.pos s i: c.1 valves, adequate verification is a l.
Except as specified in Specification 3.13.F.2 visual check of electrical below, those. sprinkler systems listed in Table indication.)
3.13.F.1 shall be operable whenever equipment in the area protected by those sprinklers is required to be operable.
Amendment No. 33', 67 9,
- 3"13 Limiting conditions for Operation-4.13 Surveillance Requirements 2.
From and af ter the date that one of the sprinkler c.
At least once per -18 months by systems specified'in Table 3.13.F.1 is
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inoperable, a fire watch shall be established 1.
Cycling each valve in the flow within one hour to inspect the location with the path that is not testable inoperable sprinkler system at least once every' during plant operation through"r sr+
hour.
Restore the sprinkler system to operable -
at least one complete cycle of
@f status within 14 days or submit a report within full travel.
the next 30 days to the Commission ca specified c3 in 6.7.C.2 outlining the cause of the malfunction 2.
A visual inspection of the and the plans for restoring the system to sprinkler headers to verify operable status.
their intergrity, and 3.
A visual inspection of each nozzle *p spray area to verify
- that the spray pattern is not obstructed.
4.
Verifying that automatic valves actuate to their correct-position from a test signal.
d.
At least once per 3 years by performing a flow test through each open head sprinkler header and verifying each open head sprinkler nozzle is unobstructed.
3.13.G roam Systems 4.13.G Foam Systems 1.
Except as specified in Specification 3.13.G.2 1.
The foam system specified in 3.13.G below, the Recirculation M.G. Set Foam System shall be demonstrated operable.
- r. hall be operable with its foam concentrate tank full (100 gallons) whenever t he Recirculation a.
At least once per 12 months by H.G. Sets are operating.
cycling each testable valve in the flow path through at least one 2.
From and af ter the date that the Recirculation complete cycle of full travel.
M.G. Set Foam System is inoperable, a fire watch shall be established to insp+ct the location at b.
At least once per 18 months by:
least once every hour s and a foam nozzle shall be brought to the Reactor Building elevation containing the Recirculation it.G. Sets.
A 100 gallon foam concentrate supply shall be.available 187-h 19:
,c 3,13 Limitinc conditions for Operation 4.13 Surveillance Requirements 3.
Except as specified in Speellication 3.13.G.4 1.
Cycling each' valve in the flow below, the Turbine Building Foam System shall be path that is not testable.
operable with its foam concentrate tank full (150 during plant operation through gallons).
at least one complete cycle of full travel.
4.
From and af ter the date that the 1brbine Building Foam System is operable a por table foam nozzle 2.
A viejal inspection of the foam shall be brought to the Turbine Building Foam
-(system and equipment to verify System location. A 150 gallon foam concentrate intergrity, and supply shall be'available en nite.
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3.
A visual-inspection of the Recirculation MG Set Foam System foani nozzle area to verify that the spray pattern
.is not obstructed.
4.
Foam concentrate-samples shall be taken and analyzed for acceptability, d.
At least once per 3 years by performing an air flow test through the Recirculation MG Set' foam header and verifying each foam nozzle is unobstructed.
Amendment No. 67 lu7. i
L VYNPS Table 3.13.A..
Fire Detection Sr. sors Minimum No. Sensors Recuired to be Coerable Sensor Location Heat Flame Smoke 1.
Cable Spreading Room & Station Battery Room 23 20
- 2..
Switchgear Poom 2
3.
Diesel Generator Room (A) 4.
Diesel Generator Room (B) 2 5.
Intake Structure. (Service Water) 1 1
1 6.
Recire Motor. Generator Set Area 3
8 14 7.a Control Room Zone 1 (Control Room Ceiling) 18 7.b Control Room Zone 2 (Control Room Panels) 7.c Control Room Zone 3 (Control Room Panels) 25 7.d Control Room Zone 4 (Control Room Panels) 10 2
7.e Control Room rone 5 (Exhaust & Supply Ducts) 1 a.a Rx Bldg. Corner Rm NW 232 1
8.b Rx Bldg. Corner Rm NW 213 (RCIC)
S.c Rx Bldg. Corner Rm NE 232 1
3.d Rn 31dg. Corner Rm NE 213 1
8.e Rx Bldg. Corner Rm SE 232 1
8.f Rx Bldg.. Corner Rm SE 213 1
89 Rx Bldg. Corner Rm SW 232 1
8 i
9.
HPCI Room i
187-j
- Amendment NO. 67
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Tdblo 3.13.A.1, c nt.
Minimum No. Sensors Recuired to be Ocerable l
Sensor' Location Heat Flame Smcke l
10.
Torus area 12 16
- 11. - Rx Bldg. Cable Penetration Arca
'7
.13 12.
Refuel Floor 1*
1*
.13. ; Diesel Oil Day Tank Room S(A)
' 14. 1 Diesel Oil Day Tank Room (B) 1*
1*
3
- 15.. Turbine Loading Bay (vehicles)
- NOTE:
The Diesel Day Tank Rooms require only one' detector operable _(1-flame or 1 smoke).
187-k Amendment No. 67 V
e
1
-v n:PS Tablo~3.13.F.l
' Sprinkler Systems
. l.-
Reactor Buildina'. Penetration Area Preaction System
- 2.
Dieeal Generator Room A System 3.
-Diesel Generator Room B System 4..
Turbine Loading Bay System
^
' 5.
Diesel-driven Fire Pump System I
1 f
1 i
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i LAmendment No. 67 187_1
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g Bases:
3.13/4.13 Fire Protection Systems P
On May 11, 1976, Vermont Yankee received a letter from the NRC requesting that an in-depth evaluation of the existing fire protection systems be performed using Branch Technical Position (BTP) APCSB 9.5-1 as a guide. Concurrent N
with this evaluation a fire hazards analysis of the entire plant complex was required.
In an effort to clarify the BTP'an Appendix A was subsequently issued to specifically address operating plants. Enclosed with this Appendix the NRC requested that proposed Technical Specifications on fire protection also be submitted. The subject section 3.13/4.13 and the following specific bases are those spelfications evolving from these efforts.
A.
The smoke, heat and flame detectors provide the early warning fire detection capability necessary to detect l
problems in' vital areas of the plant. Surveillance requirements assure these sensors and their associated instruments to be operable. When the equipment protected by the detectors is not required to be operable, specifications covering the sensors and instruments do not apply.
B,C,D, The Vital Fire Suppression Water System, CO2 systems, sprinkler systems and foam systems
- specifications are Thesesystemsprovidethe'l F and G. provided to meet pre-established Jevels of system operability in the event of a fire.
necessary protection to assure safe reactor shutdown. Periodic surveillance testing provides assurance that vital fire suppression systems are operable.
E.
Vital fire barrier penetration fire seals are provided to assure that the fire resistance rating of barriers is not reduced by a penetration. Surveillance inspections shall be performed to insure that the integrity of these seals is maintained.
The diesel fire pump has a design consumption rate of 18 gallons of fuel per hour; therefore,150 gallons provides for greater than 8 houtu of operation. Additional fuel can be delivered in about one hour and additional fuel is on site. When the equipment protected by the fire protection systesan is inst r equired t o be
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operable, the specifications governing the fire protection system do not apply.
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187-m w.